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PREPAREDI REVISE'D BY: JPM 57AP2 Page 1 of 10 Rev 3 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE
MEASURE 8.1.a JPM 57-AP2 Respond to High Containment
Pressure, Place RHR Spray in Service Date/VALIDATED BY: APPROVED BY: CONCURRED:
***(Operations
Training Manager)(Operations
Representative)
Datel Datel Date/*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual
ste.p changes that do not affect the flow of the JPM.**Operations
Concurrence
re*quired for new JPMs and changes that affect the flow of the JPM(if not driven by a procedure revision).
JPM 57AP2 Page 2 of 10 Rev 3 I NUCLEAR TRAINING REVISION/USAGE
LOG Revision Description
Pages Prepared/Number Of Revision V Date Affected Revised By: 0 Initial issue Y 12/3/01 All L.Pauley Used in 2000 NRC initial exam as 57 AP 1 Revised to latest revision of FR-Z.1 N 8/20/02 4JP Kearney 2 Made back into simulator JPM (was set up to be run in Y 8/4/05 All MG Croteau actual MCR).Set up for current IC and procedure revision.Updated references, wrote and referenced
SCENS file N 10/20105 3,4 JJ Tricoglou 3 Reworded turnover information, referenced
FR-Z.1 rev 4,10 17, revised instructions, added handout sheet, modified standards wording.v-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.-
JPM 57AP2 Page 3 of 10 Rev 3 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE
MEASURE Task: Respond to High Containment
Pressure, Place RHR Spray in Service Note: This JPM satisfies Simulator Manipulation"IN13".JAITA task#: 3110160601
KIA Ratings: 022000 A3.01 (4.1-4.4)026000 GA 13 (3.6-3.6)(RO)022000 A4.04 (3.1-3.20 026000 GAg (3.6-3.6)Task Standard: Attempt to establish one train of RHR spray in service per FR-Z.1.Evaluation
Method: Simulator__X__In-Plant.:..-==========="========================================================================
Performer:
Performance
Rating: SAT Evaluator:
NAME UNSAT SIGNATURE Performance
Time DATE Start Time_Finish Time_===================================================================================
COMMENTS
JPM 57AP2 Page 4 of 10 Rev 3 SPECIAL INSTRUCTIONS
TO EVALUATOR:
1.Sequenced steps identified
by an"s" 2.Any UNSAT requires comments 3.Initialize
simulator in IC#176.If Ie 176 is not available the reset to IC#24 and complete substeps below.a.Activate MF#TH01A at 350/0.b.Activate MFs#CH01 A thru D at 70%(-10.2 psid)c.Complete the actions of ES-1.3, Sump Swapover.Stop RCPs.d.Activate Override ZDIHS6393A
OPEN, to prevent FCV-63-93 from closing.e.Activate Override ZDIHS7241A
CLOSE*, to prevent FCV-72-41 from opening.4.Activate the following, as necessary, to prevent nuisance alarms:*AN:OVRN[96]
to OFF, prevents Turbine Zero Speed alarm**AN:OVRN[214]
to OFF, prevents Saturation
Monitor alarm*AN:OVRN[304]
to OFF, prevents MFP Lo NPSH*AN:OVRN[2155]
to OFF, prevents SG Pressure Lo 5.Insert Remote Function RHR14 ON, places power on FCV-63-1.6.FREEZE the simulator until the operator is ready to commence task.7.Console operator will need to acknowledge
alarms*not associated
with JPM.8.Ensure operator performs the following required actions for SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.8 mins Tools/Equipment/Procedures
Needed: FR-Z.1, step 13 References:
Local-----Reference FR-Z.1 Title Hi h Containment
Pressure Rev No.17===========,===============================================================================
READ TO OPERATOR Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Unit 1 has experienced
a reactor trip and Safety Injection in conjunction
with a large break LOCA.2.The crew has been monitoring
step 13 of FR-Z.1 since FR-Z.1 was implemented.
3.1 hour has elapsed since the accident.INITIATING
CUES: 1.The US directs you to perform FR-Z.1, Step 13 to initiate one train of RHR spray.2.Inform the US when Step 13 has been completed.
Job Performance
Checklist STEP/STANDARD
JPM 57AP2 Page 5 of 10 Rev 3 SAT/UNSAT STEP 1.: Obtain copy of appropriate
procedure.
-SAT Cue: After operator locates FR-Z.1 procedure, provide a copy of-UNSAT FR-Z.1 marked up as appropriate.
Start Time--STANDARD: Operator obtains a copy of FR-Z.1 (begin at Step 13).COMMENTS: STEP 2.:[FR-Z.1, Step 13]MONITOR if RHR Spray should be placed in-SAT service.-UNSAT CHECK Containment
press greater than 9.5 psid.STANDARD: Operator checks PDIS-30-42
through 45 and determines
that pressure is greater than 9.5.COMMENTS: STEP 3.: CHECK at least 1 hour has elapsed since beginning of accident.-SAT Cue: IF asked, 1 hour has elapsed since beginning of accident.-UNSAT STANDARD: Operator determines
from initiating
cues (or asks US)that 1 hour has elapsed.COMMENTS: STEP 4.: CHECK RHR suction ALIGNED to containment
sump.-SAT Cue: If asked, ES-1.3 has been completed.
-UNSAT STANDARD: Operator check FCV-63-72 and 73 open AND FCV-74-3 and 21 closed.OR asks US if ES-1.3"Transfer to RHR Containment
Sump" has been completed.
COMMENTS:
Job Performance
Checklist STEP/ST AN DARD JPM 57AP2 Page 6 of 10 Rev 3 SAT/UNSAT STEP 5.: CHECK at least one CCP AND one SI pump RUNNING.-SAT STANDARD: Operator ensures at least one CCP is running as indicated by red-UNSAT light on 1-HS-62-1 04A or 1-HS-62-1 08A LIT.AND Ensures at least one SI pump is running as indicated by red lights on 1-HS-63-1 OA or 1-HS-63-15A"LIT".COMMENTS: STEP 6.:[13.b]CHECK
both RHR pumps RUNNING.-SAT STANDARD: Operator checks that both RHR pumps are running as indicated by red-UNSAT lights on
1-HS-20A"LIT".COMMENTS: STEP 7.:[13.c]ESTABLISH Train B RHR spray:-SAT 1.CHECK Train B RHR pump RUNNING.-UNSAT STANDARD: Operator checks that 1 B-B RHR pump is running as indicated by red light on 1-HS-74-20A"LIT".COMMENTS: STEP 8.:[13.c.2)]ENSURE RHR crosstie FCV-74-35 CLOSED.-SAT STAN'DARD:
Operator verifies FCV-74-35 in the CLOSE position as indicated by-UNSAT 1-HS-74-35A
green light ON and red light off.COMMENT.S:
STEP 9.:[13.c.3)]CLOSE RHR Injection FGV-63-94.
-SAT-UNSAT STANDARD: Operator places handswitch
1-HS-63-94A
for RHR injection FCV-63-94 in the CLOSE position.Critical Step COMMENTS:
JobPerformance
Checklist STEP/STANDARD
JPM 57AP2 Page 7 of 10 Rev 3 SAT/UN SAT NOTE: This is the alternate path.-SAT STEP 10.:[13.c.4)]OPEN RHR Spray FCV-72-41.
-UNSAT NOTE: FCV-72-41 will NOT open the operator must go to the RNO and align the A train RHR spray.STANDARD: Operator places handswitch1-HS-72-41A
for RHR injection FCV-72-41 in the OPEN position and recognizes
that the green light stays ON and the red light is OFF, goes to RNO column.COMMENTS: NOTE: The following steps are from FR-Z.1, step 13.c RNO-SAT STEP 11.:[13.c RNO a)]ENSURE RHR Spray FCV-72-41 CLOSED.-UNSAT STANDARD: Operator verifies FCV-72-41 is closed as indicated by green light ON and red light OFF on 1-HS-72-41A.
COMMENTS: STEP 12.:[13.c RNO b)]IF RHR aligned for cold leg recirculation, THEN-SAT ENSURE FCV-63-94 OPEN.-UNSAT STANDARD: Operator places handswitch
1-HS-63-94A
for RHR injection FCV-63-94 in the OPEN position.Critical Step COMMENTS: STEP 13.:[13.c RNO c)]ESTABLISH Train A RHR spray:-SAT (1)ENSURE RHR crosstie
CLOSED.-UNSAT STANDARD: Operator verifies RHR crosstie FCV-74-33 in the CLOSE position as indicated by green light LIT on handswitch
1-HS-74-33A.
COMMENTS:
Job Performance
Checklist STEP/STANDARD
JPM 57AP2 Page 8 of 10 Rev 3 SAT/UNSAT STEP 14.:[13.c RNO c)(2)]CLOSE RHR Injection FCV-63-93.
-SAT-UNSAT STANDARD: Operator places handswitch
1-HS-63-93A
for RHR injection FCV-63-93 in the CLOSE position.Critical COMMENTS: Step STEP 15.: OPEN RHR spray FCV-72-40.
-SAT STANDARD: Operator places handswitch
1-HS-72-40A
for FCV-72-40 in the-UNSAT OPEN position.Critical Step COMMENTS: STEP 16.:[13.d]MONITOR containment
pressure greaterthan
4 psig.-SAT-UNSAT STANDARD: Operator checks PDIS-30-42
through 45 and determines
that pressure is greater 4 psig and continues to the next step.This completes Step 13 and the JPM COMMENTS: STEP 17.: Communicates
with SRO and informs him RHR spray status.-SAT-UNSAT STANDARD: Operator informs SRO that the Train A RHR spray has been placed in service in accordance
with FR-Z.1 and that FCV-72-41 failed to open.Stop Time__COMMENTS: END OF JPM
ECCS Simplified
Drawing*------------1
*I I I*I*I*I*I*I11: 63-1j:£: i i:._________i FCV-74-24.-£:: FCV:: 74-12:*.*.*.*.: RHR:*.*.I**.I: "------i Fev 63-172 Hot Legs Loops: 1&3 Hot Legs Loops:..._-----_._----_.
__._--------_
.._-_._.._-_.__.._---..__
..-Cold Legs.I1 FCV[j63_22 FCV i FCV.......L--__Charging
...........
[.._...._.*............................................................
__.--_.-_.-..----l**L**'" LCV._11 LCV 62-135..LJ62.136..----1-*----*
Hot Legs*.Loops&3';""...........
v C T FCV 63-156.LCV.r-I62-133 r***
------,
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION
OF TASK)DIRECTION TO T*RAINEE: I will explain the initial conditions, a.nd state the task to be performed.
All control room steps shall be performed for this.JPM, including any required communications.
I will provide initiating
cues and reports on other actions when directed by you.Ensure you indicate to me when you understand
your assigned task.To indicate that you have com*pleted
your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Unit 1 has experienced
a reactor trip and Safety Injection in conjunction
with a large break LOCA.2.The crew has been monitoring
step 13 of FR-Z.1 since FR-Z.1 was implemented.
3.1 hour has elapsed since the accident.INITIATING
CUES: 1.The US directs you to performFR-Z.1, Step 13 to initiate one train of RHR spray.2.Inform the US when Step 13 has been completed.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL FUNCTION RESTORATION
PROCEDURE FR-Z.1 HIGH CONTAINMENT
PRESSURE Revision 17 QUALITY RELATED D.A.PORTER PREPARED/PROOFREAD
BY:-----------
RESPONSIBLE
ORGANIZATION:
OPERATIONS
----------
w.T.LEARY APPROVED BY:---------------
EFFECTIVE DATE: 05/31/07 REVISION DESCRIPTION:
Updated ES-1.3 step number reference in Step 5.c RNO.This procedure contains a Handout Page (2 copies).
SQN STEP I HIGH CONTAINMENT
PRESSURE HANDOUT Page 1 of 1 ACTION FR-Z.1 Rev.17 1.4.d RNO 6.10.RNO.12.12.a RNO 12.d 13.MONITOR RWST level greater than 27%.(if any S/G is faulted and air return fans are NOT running)WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment
air return fans running.MONITOR containment
air return fans:*WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment
air return fans running.IF all S/Gs Faulted, THEN CONTROL feed flow at greater than or equal to 25 gpm to each S/G.MONITOR if hydrogen igniters and recombiners
should be turned on: WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN CHECK if hydrogen igniters and recombiners
are required.WHEN ice condenser AHU breakers are open, THEN ENERGIZE hydrogen igniters (if hydrogen concentration
less than 6%).MONITOR if RHR spray should be placed in service:*Containment
pressure greater than 9.5 psig***AND at least 1 hour has elapsed since
of accident AND RHR suction ALIGNED to containment
sump AND at least one CCP AND one SI pump RUNNING.13.d.(if RHR spray in service)RNO WHEN Containment
pressure is less than 4 psig, THEN REMOVE RHR spray from service.14.MONITOR if containment
spray should be stopped: (containment
pressure less than 2.0 psig)14.c (if containment
spray suction aligned to sump)RNO WHEN directed by TSC, THEN STOP containment
spray.1a of 16
SQN STEP i HIGH CONTAINMENT
PRESSURE HANDOUT Page 1 of 1 ACTION FR-Z.1 Rev.17 1.4.d RNO 6.10.RNO.12.12.a RNO 12.d 13.MONITOR RWST level greater than 27%.(if any S/G is faulted and air return fans are NOT running)WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment
air return fans running.MONITOR containment
air return fans:*WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment
air return fans running.IF all S/Gs Faulted, THEN CONTROL feed flow at greater than or equal to 25 gpm to each S/G.MONITOR if hydrogen igniters and recombiners
should be turned on: WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN CHECK if hydrogen igniters and recombiners
are required.WHEN ice condenser AHU breakers are open, THEN ENERGIZE hydrogen igniters (if hydrogen concentration
less than 6%).MONITOR if RHR spray should be placed in service:*Containment
pressure greater than 9.5 psig***AND at least 1 hourhaselapsed
since beginning of accident AND RHR suction ALIGNED to containment
sump AND at least one CCP AND one SI pump RUNNING.13.d.(if RHR spray in service)RNO WHEN Containment
pressure is less than 4 psig, THEN REMOVE RHR spray from service.14.MONITOR if containment
spray should be stopped: (containment
pressure less than 2.0 psig)14.c (if containment
spray suction aligned to sump)RNO WHEN directed by TSC, THEN STOP containment
spray.1b of 16
SQN 1.0 PURPOSE HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 This procedure provides actions to respond to a high containment
pressure.2.0 SYMPTOMS AND ENTRY CONDITIONS
2.1 ENTRY CONDITIONS
FR-O Status Trees:*F-O.5, Containment
RED condition:
Containment
pressure greater than or equal to 12.0 psig.*F-O.5, Containment
ORANGE condition:
Containment
pressure less than 12.0 psig AND Containment
pressure greater than or equal to 2.8 psig.3.0 OPERATOR ACTIONS Page 2 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE I I RESPONSE NOT OBTAINED NOTE If this procedure has been entered for an orange path and performance
of ECA-1.1 (Loss of RHR Sump Recirculation)
is required, FR-Z.1 may be performed concurrently
with ECA-1.1.1.2.MONITOR RWST level greater than 27%.VERIFY Phase B valves CLOSED: Panel 6K PHASE B GREEN Panel 6L PHASE B GREEN.IF ES-1.3 has NOT been entered, THEN GO TO ES-1.3, Transfer to RHR Containment
Sump.----..---IF 1-FCV-32-110
(2-FCV-32-111)
&is NOT closed, THEN PERFORM EA-32-3, Isolating Non-Essential
Air to Containment.
IF other valves NOT closed AND flow path is NOT necessary, THEN CLOSE valves.3.ENSURE RCPs STOPPED.Page 3 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 4.DETERMINE if this procedure should be exited: a.CHECK for faulted S/G: a.GO TO Step 5..Any S/G pressure DROPPINGin an uncontrolled
manner OR.Any S/G pressure less than 140 psig.b.CHECK containment
pressure b.GO TO Step 5.less than 12 psig.=--c.CHECK at least one containment
spray pump RUNNING and delivering
flow.d.CHECK at least one containment
air return fan RUNNING.e.RETURN to procedure and step in effect.----.---c.IF containment
pressure is greater than 2.8 psig, THEN GO TO Step 5.d.WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE air return fans RUNNING.Page 4 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 5.VERIFY containment
spray operation:
a.CHECK RHR sump recirculation
capability
AVAILABLE.
b.VERIFY containment
spray pumps RUNNING.c.CHECK RWST level greater than 27%.II RESPONSE NOT OBTAINED a.IF ECA-1.1 , Loss of RHR Sump Recirculation, is IN EFFECT, THEN PERFORM the following:1)OPERATE containment
spray as directed by ECA-1.1.2)GO TO Step 6.b.IF containment
pressure is greaterthan2.8 psig, THEN START containment
spray pumps.c.IF any of following conditions
met:*RWST level less than or equal to 8%OR*containment
sump level greater than 560/0, THEN PERFORM the following:
1)ENSURE cntmt spray pump suction aligned for sump recirc USING ES-1.3, Transfer to RHR Containment
Sump, Step 21.2)GOTO Substep 5.e.(step continued on next page)Page 5 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17.I STEP I I ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 5.d.VERIFY containment
spray suction ALIGNED to RWST:*FCV-72-22 OPEN*FCV-72-21 OPEN.d.ALIGN valves as necessary.
e.VERIFY containment
spray discharge e.OPEN valves for running valves OPEN: containment
spray pumps.*FCV-72-39*FCV-72-2.f.VERIFY containment
spray recirc valves CLOSED:*FCV-72-34*FCV-72-13.
g.VERIFY containment
spray flow greater than 4750 gpm on each train.f.CLOSE valves as necessary.
g.IF NO train of containment
spray is available, THEN PERFORM the following:
1)CONTINUE efforts to restore at least one train of containment
spray.2)NOTIFY TSC to evaluate restoring normal containment
cooling USING EA-30-4, Restoring Containment
Coolers.Page 6 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEP I I ACTION/EXPECTED
RESPONSE 6.MONITOR containment
air return fans:*WHEN at least 10 minutes have elapsed from Phase B, THEN ENSURE containment
air return fans RUNNING.II RESPONSE NOT OBTAINED 7.8.9.VERIFY containment
ventilation
dampers CLOSED: Panel 6K CNTMT VENT GREEN Panel6L CNTMT VENT GREEN.VERIFY Phase A valves CLOSED: Panel 6K PHASE A GREEN Panel6L PHASE A GREEN.VERIFY MSIVs and MSIVbypassvalves
CLOSED.CLOSE dampers.IF flow path NOT necessary, THEN CLOSE valves.CLOSE valves.IF any MSIV CANNOT be closed, THEN CLOSE MSIV locally USING EA-1-1, ClosingMSIVsLocally.
Page 7 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 10.DETERMINE if any S/G Intact: a.CHECK at least one S/G pressure:*CONTROLLED
or RISING AND*Greater than 140 psig.II RESPONSE NOT OBTAINED IF all S/Gs Faulted, THEN PERFORM the following:
1)CONTROL feed flow at greater than or equal to 25 gpm to each S/G.2)OPEN MD AFW pump recirc valves FCV-3-400 and-401 as necessary.
3)GO TO Step 12.CAUTION Isolating all S/Gs will result in a loss of secondary heat sink.11.DETERMINE if any S/G Faulted: a.CHECK S/G pressures:
*Any S/G pressure DROPPING in an uncontrolled
manner OR*Any S/G pressure less than 140 psig.b.ISOLATE feed flow to affected S/G: MFW*AFW Page 8 of 16 a.GO TO Step 12.
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 12.MONITOR if hydrogen igniters and recombiners
should be turned on: a.DISPATCH personnel to open ice condenser AHU breakers USING EA-201-1, 480 V Board Room Breaker Alignments.
b.CHECK hydrogen concentration
measurement
AVAILABLE:
*Hydrogen analyzers have been in ANALYZE for at least 5 minutes.c.CHECK containment
hydrogen concentration
less than 6%.d.WHEN ice condenser AHU breakers have been opened, THEN ENERGIZE hydrogen igniters USING Appendix D, Placing Hydrogen Analyzers and Igniters In Service.II RESPONSE NOT OBTAINED b.PERFORM the following:
1)DISPATCH operator to place hydrogen analyzers in service USING Appendix D.(also contained in ES-0.5)2)WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN PERFORM substeps 12.c through 12.e.3)GO TO Step 13.=---c.CONSUL T TSC.GO TO Step 13.=---(Step continued on next page.)Page 9 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEP I I ACTION/EXPECTED
RESPONSE 12.e.CHECK containment
hydrogen concentration
less than 0.5%.13.MONITOR if RHR spray should be placed in service: a.CHECK the following:
Containment
pressure greater than 9.5 psig AND At least 1 hour has elapsed since beginning of accident AND RHR suction ALIGNED tocontainmentsump
AND At least one CCP AND one SI pump RUNNING.II RESPONSE NOT OBTAINED e.PLACE hydrogen recombiners
in service USING EA-268-1, Placing Hydrogen Recombiners
in Service.IF hydrogen recombiners
NOT available, THEN CONSULT TSC.a.GO TO Step 14.(Step continued on next page.)'Page 10 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 13.b.CHECK both RHR pumps RUNNING.b.IF only one RHR pump running, THEN PERFORM the following:
1)ENSURE only one CCP RUNNING (same train as running RHR pump preferred).
2)PLACE non-operating
CCP in PULL TO LOCK.3)ENSURE only one SI pump RUNNING (same train as running RHR pump preferred).
4)PLACE non-operating
SI pump in PULL TO LOCK.(Step continued on next page.)Page 11 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 13.c.ESTABLISH Train B RHR spray: 1)CHECK Train B RHR pump RUNNING.2)ENSURE RHR crosstie FCV-74-35 CLOSED.3)CLOSE RHR injection FCV-63-94.
4)OPEN RHR spray FCV-72-41.
II RESPONSE NOT OBTAINED c.IF Train B RHR spray CANNOT be established, THEN PERFORM the following:
a)ENSURE RHR spray FCV-72-41 CLOSED.b)IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-94 OPEN.c)ESTABLISH Train A RHR spray: (1)ENSURE RHR crosstie FCV-74-33 CLOSED.(2)CLOSE RHR injection FCV-63-93.
(3)OPEN RHR spray FCV-72-40.
IF Train A RHR spray.CANNOT be established, THEN PERFORM the following:
a)CLOSE RHR spray FCV-72-40.
b)IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 OPEN.(Step continued on next page.)Page 12 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 13.d.MONITOR containment
pressure greater than 4 psig.II RESPONSE NOT OBTAINED d.WHEN containment
pressure is less than 4 psig, THEN PERFORM the following:
1)ENSURE FCV-72-40 and FCV-72-41 CLOSED.2)IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 and FCV-63-94 OPEN.3)IF ECCS is aligned for hot leg recirculation, THEN ENSURE RHR crosstie valves FCV-74-33 and FCV-74-35 aligned as required by ES-1.4.Page 13 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 14.MONITOR if containment
spray should be stopped: a.CHECK any containment
spray pump RUNNING.b.CHECK containment
pressure less than 2.0 psig.c.CHECK containment
spray suction aligned to RWST.d.RESET Containment
Spray.e.STOP containment
spray pumps and PLACE in A-AUTO.f.CLOSE containment
spray discharge valves:*FCV-72-39, Train A*FCV-72-2, Train B.II RESPONSE NOT OBTAINED a.GO TO Step 15.b.GO TO Step 15.c.NOTIFY TSC to determine when one or both trains of cntmt spray should be stopped.WHEN directed by TSC, THEN PERFORM Substeps 14.d through 14.f.GO TO Step 15.Page 14 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 15.RETURN TO procedure and step in effect.----..---II RESPONSE NOT OBTAINED END Page 15 of 16
SQN HIGH CONTAINMENT
PRESSURE FR-Z.1 Rev.17 Page 1 of 1 APPENDIX D PLACING HYDROGEN ANALYZERS AND IGNITERS IN SERVICE 1.PLACE hydrogen analyzers in service: a.ENSURE the following switches in ANALYZE position:[M-10]*HS-43-200A, Cntmt H2 Analyzer Fan A*HS-43-210A, Cntmt H2 Analyzer Fan B.b.RECORD time:_c.NOTIFY Unit Supervisor
of time that hydrogen analyzers were placed in ANALYZE.D D D D NOTE The following step is performed when directed by an EOP step (after hydrogen concentration
has been verified and ice condenser AHU breakers have been opened).2.WHEN directed to energize hydrogen igniters, THEN ENSURE the following switches in ON position:[M-10]*HS-268-73, H2 Igniters Group A*HS-268-74, H2 Igniters Group B.END OF TEXT Page 16 of 16 D D
PREPAREDI REVISED BY: VALIDATED BY:*APPROVED BY: JPM B.1.b Page 1 of 11 Rev.0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE
MEASURE B.1.b JPM Respond to a#1 Rep Seal Failure Date/Date/Date/(Operations
Training Manager)CONCURRED:
**Date/(Operations
Representative)
*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual
step changes that do not affect the flow of the JPM.**Operations
Concurrence
required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM B.1.b Page 2 of 11 Rev.0 NUCLEAR TRAINING REVISION/USAGE
LOG REVISION DESCRIPTION
OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 New, modifiedfromJPM 403 Y Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.
JPM B.1.b Page 3 of 11 Rev.0 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE
MEASURE Task: Respond to an RCP Seal Failure JAITA task:#0000820501 (RO)KIA Ratings: 003 Reactor Coolant Pump System A2.01 3.5/3.9 Task Standard: 1)Candidate determines
the#1 RCP has a seal malfunction
and enters AOP-R.04 2)Candidate trips reactor, removes the#1 RCP from service, and closes the seal return valve from the pump.Evaluation
Method: Simulator__X__In-Plant_===================================================================================
Performer:
Performance
Rating: SAT NAME UNSAT Performance
Time Start Time_Finish Time_Evaluator:
-------------_/_--
SIGNATURE DATE===================================================================================
COMMENTS
JPM B.1.b Page 4 of 11 Rev.0 SPECIAL INSTRUCTIONS
TO EVALUATOR:
1.Sequenced steps identified
by an"s" 2.Any UNSAT requires comments 3.This task is to be performed using the simulator in IC-10, 14%power ready to roll turbine 4.Put MODE 1 sign on simulator 5.When ready to start, insert malfunction
CV17 A f: 0.60 6.Ensure operator performs the following required actions for SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.14 min Local-----Tools/Equipment/Procedures
Needed: AOP-R.04 References:
1.AOP-R.04 Reference Title Reactor Coolant Pum Malfunctions
Rev No.22=============================================================================
READ TO OPERATOR Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Unit 1 is in MODE 1 at 140/0 reactor power preparing to roll the main turbine.Currently awaiting completion
of maintenance
activities.
INITIATING
CUES: 1.You are the OATC and are to monitor the control board and respond to conditions
as required.This JPM contains Time Critical steps
Job Performance
Checklist STEP/STANDARD
JPM B.1.b Page 5 of 11 Rev.0 SAT/UNSAT STEP 1.: Obtain the appropriate
procedure.
SAT UNSAT STANDARD: Operator identifies
window B-3, FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW lit and uses 1-AR-M5-B to respond.The following 2 steps are from 1-AR-M5-B Window B-3 STEP 2.:[1]Verify High Leakoff condition on affected RCP(s)with the following instruments
Start Time__SAT UNSAT Pump RCP 1 RCP2 RCP3 RCP4 Leakoff Instrumentation
1-FR-62-24
1-FR-62-24
1-FR-62-50
1-FR-62-50
f STANDARD: Candidate determines
that#1 RCP has high Seal flow on 1-FR-62-24
or by looking at the ICS.COMMENTS: STEP 3.:[2]GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
STANDARD: Candidate enters AOP-R.04 COMMENTS: The following steps are from AOP-R.04 STEP 4.: 1.DIAGNOSE the failure: STANDARD: Candidate determines
Section 2.2 is the appropriate
section and goes to section 2.2 COMMENTS: SAT UNSAT SAT UNSAT
Job Performance
Checklist STEP/STANDARD
JPM B.1.b Page 6 of 11 Rev.0 SAT/UNSAT STEP 5.: 1.MONITOR#1 sealleakoff
less than 6 gpm per pump:-SAT*FR-62-24[RCP1&2]-UNSAT*FR-62-50[RCP3&4]STANDARD: Candidate uses 1-FR-62-24
or by looking at the ICS to determine seal flow on#1 RCP is greater than 6 gpm and goes to the RNO.COMMENTS: STEP 6.: a.MONITOR RCP lower bearing temperature
and seal temperature.
-SAT IF RCP lower bearing temperature
OR seal temperature
are rising-UNSAT uncontrolled, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1][C.2]STANDARD: Candidate uses 1-TI-62-3 and 1-TI-62-4 to determine lower bearing temperature
and seal temperature
are rising and goes to Section 2.1, Reactor Coolant Pump(s)Tripped or Shutdown Required COMMENTS: STEP 7.: 1.CHECK reactor power greater than 10%-SAT-UNSAT STANDARD: Candidate determines
reactor power is greater than 100/0 and continues to the next step.COMMENTS:
Job Performance
Checklist STEP/STAN DARD STEP 8.: 2.TRIP the reactor and GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing
in this procedure.
After candidate completes the immediate actions, state that the SRO and another operator will perform E-O.STANDARD: Candidate trips the reactor by placing reactor trip switch to the trip position.COMMENTS: STEP 9.: 3.STOP and LOCK OUT affected RCP(s).STANDARD: Candidate places handswitch
1-HS-68-8A
to the stop position (critical).
Handswitch
placed in the Pull to Lock position (non-critical).
Record time pump is stopped_COMMENTS: STEP 10.: 4.MONITOR RCP sealleakoff
less than 8 gpm per pump:*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]Evaluator Note: Scale on recorder is 0-10 gpm STANDARD: Candidate determines
that#1 RCP sealleakoff
flow on 1-FR-62-24
is greater than 8 gpm.COMMENTS: JPM B.1.b Page 7 of 11 Rev.0 SAT/UNSAT SAT UNSAT Critical Step SAT UNSAT Critical Step SAT UNSAT
Job Performance
Checklist STEP/STANDARD
STEP 11.: WHEN the RCP has coasted down (30 sec.), THEN CLOSE affected RCP seal return FCV:[C.2]*FCV-62-9[RCP 1]*FCV-62-22[RCP 2]*FCV-62-35[RCP 3]*FCV-62-48[RCP 4]STANDARD: Candidate place 1-HS-62-9 to the Close position within 5 minutes of stopping the RCP Record time FCV is closed_COMMENTS: STEP 12.: 5.PULL TO DEFEAT affected loop 1\T and T-avg:*XS-68-2D (1\T)*XS-68-2M (T-avg)STANDARD: Candidate places 1-XS-68-2D
and 1-XS-68 2M to Loop 1 position and pulls each out.COMMENTS: STEP 13.: 6.CHECK RCPs 1 and 2 RUNNING.STANDARD: Candidate determines
that#1 Reactor coolant pump is not running.COMMENTS: STEP 14.: 6.RNO CLOSE affected loop's pressurizer
spray valve.STANDARD: Candidate verifies Loop 1 PZR Spray Valve 1-PIC68-340D
is closed.May place the controller
to manual.COMMENTS: JPM B.1.b Page 8 of 11 Rev.0 SAT/UNSAT SAT UNSAT Critical Step Time Critical Step SAT UNSAT SAT UNSAT SAT UNSAT
Job Performance
Checklist STEP/STANDARD
STEP 15.: 7.IF RCP Seal T em peratures or Bearing Tem peratures are increasing
uncontrolled
due to loss of Seal Injection, THEN EVALUATE initiating
RCS cooldown.Cue: When step addressed state"Shift Manager is evaluating
the need to cooldown" STANDARD: Candidate addresses the need for the cooldown evaluation.
COMMENTS: STEP 16.: 8.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.Cue: When step addressed state"Shift Manager will evaluate EPIPs" STANDARD: Candidate addresses the step COMMENTS: STEP 17.: 9.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant System-Hot Standby*3.4.1.3, Reactor Coolant System-Shutdown*3.4.6.2, RCS Operational
Leakage Cue: When step addressed state"SRO will evaluate Tech Specs" STANDARD: Candidate notifies SRO to evaluate Tech Spec.COMMENTS: JPM B.1.b Page 9 of 11 Rev.0 SAT/UNSAT SAT UNSAT SAT UNSAT SAT UNSAT
Job Performance
Checklist STEP/STANDARD
STEP 18.: 10.GO TO appropriate
plant procedure.
END OF SECTION Cue: To candidate"'We will stop here" STANDARD: Candidate recognizes
that a transition
from the AOP is required.End of JPM JPM B.1.b Page 10 of 11 Rev.0 SAT/UNSAT SAT UNSAT Stop Time__
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION
OF TASK)Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Unit 1 is in MODE 1 at 14%reactor power preparing to roll the main turbine.Currently awaiting completion
of maintenance
activities.
INITIATING
CUES: 1.You are the OATe and are to monitor the control board and respond to conditions
as required.This JPM contains Time Critical steps
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOI PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES
AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS
Revision 22 QUALITY RELATED PREPARED/PROOFREAD
BY: D.A.PORTER RESPONSI BLE ORGAN IZATION: OPERATIONS
APPROVED BY: W.T.LEARY EFFECTIVE DATE: 12/19/2005
REVISION DESCRIPTION:
Revised to clarify actions if neither RCP lower bearing temperature
nor RCP seal temperature
indication
is available (PER 93845).Corrected inconsistency
between caution in Section 2.0 and Appendix B.
SQN 1.0 PURPOSE REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 This procedure provides the actions necessary to mitigate the effects of a Reactor Coolant Pump (RCP)trip below P-8 (35%power), excessive RCP seal leakage, and various RCP malfunctions.
Page 2 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.0 OPERATOR ACTIONS RESPONSE NOT OBTAINED CAUTION: Exceeding the following limitations
requires trip of the affected RCP, unless RCP operation is required by FR-C.1, Inadequate
Core Cooling or FR-C.2, Degraded Core Cooling:*RCP#1 Seal less than 220 psid*RCP#1 Seal Temperature
greater than 225°F*RCP Lower Bearing Temperature
greater than 225°F*RCP Upper Motor Bearing Temperature
greater than 200°F*RCP Lower Motor Bearing Temperature
greater than 200°F*RCP Motor Voltage less than 5940V or greater than 7260V*RCP Motor Amps greater than 608 amps*RCP Vibration greater than 20 mils on any axis (x and/or y)[C.3]NOTE 1: During plant startup following seal maintenance, the seal package should seat and operate normally following 24 hours of run time.NOTE 2: RCP trip criteria is also located in Appendix B.This appendix should be referred to throughout
the performance
of this procedure.
1.DIAGNOSE the failure: IF...GOTO SECTION PAGE Reactor Coolant Pump(s)tripped or shutdown required 2.1 4 RCP#1 Seal Leakoff high flow (high flow Alarm)2.2 7 RCP#1 Seal Leakoff low flow (low flow Alarm)2.3 13 RCP#2 Seal Leakoff high flow (high RCP standpipe level)2.4 17 RCP#3 Seal Leakoff high flow (low RCP standpipe level)2.5 20 RCP Motor Stator Temperature
High 2.6 23 Page 3 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is tripped.1.CHECK reactor power greater than 10%.SHUT DOWN to MODE 3 within 1 hour.GO TO Step 3.NOTE: This procedure is intended to be performed concurrently
with E-O, Reactor Trip or Safety Injection.
2.TRIP the reactor, and GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing
in this procedure.
___11"---3.STOP and LOCK OUT affected RCP(s).Page 4 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required (cont'd)CAUTION: If the RCP seal return flow control valve (FCV)is NOT closed within 5 minutes of stopping the Rep with excessive leakoff, seal damage may occur.[C.2]4.MONITOR RCP seal leakoff less than 8 gpm per pump:*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]5.PULL TO DEFEAT affected loopT and T-avg:*XS-68-2D*XS-68-2M (T-avg)6.CHECK RCPs 1 and 2 RUNNING.WHEN the RCP has coasted down (30 sec.), THEN CLOSE affected RCP seal return FCV:[C.2]*FCV-62-9[RCP 1]*FCV-62-22[RCP 2]*FCV-62-35[RCP 3]*FCV-62-48[RCP 4]CLOSE affected loop's pressurizer
spray valve.Page 5 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required (cont'd)CAUTION: Restoring seal water injection to a hot seal package could result in failure of the RCP seals.NOTE: The plant should be cooled down to reduce heat input into the pump seal package if RCP seal injection flow has been lost and cannot be restored prior to exceeding temperature
limits.7.IF RCP Seal Temperatures
or Bearing Temperatures
are increasing
uncontrolled
due to loss of Seal Injection, THEN EVALUATE initiating
RCS cooldown.8.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.9.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational
Leakage 10.GO TO appropriate
plant procedure.
___111"---END OF SECTION Page 6 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.2 RCP#1 Seal Leakoff High Flow RESPONSE NOT OBTAINED*CAUTION:*CAUTION: RCP bearing damage may occur if temperature
exceeds 225°F.If the RCP seal return flow control valve is NOT closed within 5 minutes of stopping the RCP with excessive leakoff, seal damage may occur.[C.2]1.MONITOR#1 seal leakoff less than 6 gpm per pump:*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]a.MONITOR RCP lower bearing temperature
and seal temperature.
IF RCP lower bearing temperature
OR seal temperature
are rising uncontrolled, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1][C.2]----=---IF lower bearing temperature
AND seal temperature
indication
are NOT available for affected RCP, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]..(Step continued on next page.)Page 7 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE ,.2.2 RCP#1 Seal Leakoff High Flow (cont'd)1.(Continued)
RESPONSE NOT OBTAINED b.CHECK#1 seal leakoff flow: IF#1 seal leakoff flow greater than 8 gpm, THEN PERFORMthefollowing:
1)INITIATE plant shutdown at 2-5%per minute USING AOP-C.03, Emergency Shutdown.2)WHEN reactor is tripped, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]___;11--..IF#1 sealleakoff
flow less than 8 gpm, THEN PERFORM the following:
1)CONTROL RCP seal injection flow for the affected RCP greater than or equal to 9 gpm.2)CONTACT Engineering
for recommendations
WHILE continuing
with this procedure.(Step continued on next page.)Page 8 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)1.(Continued)
2.MONITOR RCP lower bearing and seal water temperatures
less than 225°F.Page 9 of 34 RESPONSE NOT OBTAINED 3)IMPLEMENT Engineering
recommendations
to address specific RCP seal performance
conditions.
OR COMPLETE normal plant shutdown within 8 hours USING appropriate
plant procedure.
4)WHEN reactor is shutdown or tripped, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]--_..IF any of the following conditions
met:*RCP lower bearing temperature
or seal water temperature
greater than 225°F OR*seal leakoff flow greater than 6 gpm AND lower bearing and seal temp NOT available for affected RCP THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)3.MONITOR RCP#1 seal ilP greater than 220 psid:*PDI-62-8A*PDI-62-21A
*PDI-62-34A
*PDI-62-47A
4.ENSURE RCP seal water supply flow 6-10 gpm per pump:*FI-62-1A*FI-62-14A*FI-62-27A*FI-62-40A 5.CONTACT Engineering
for recommendations
WHILE continuing
with this procedure.
6.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.RESPONSE NOT OBTAINED GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]___:e---IF seal water supply flow is less than 6 gpm AND CANNOT be restored, THEN ENSURE CCS supply to thermal barriers is less than 105°F:*TR-70-161[CCS HX1A1(2A1)/1A2(2A2)
Outlet Temp]Page 10 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)7.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational
Leakage RESPONSE NOT OBTAINED CAUTION: Slow and uniform temperature
adjustments (approx.50°F in one hour)will prevent thermal shock to the seals.8.CHECK VCT outlet temperature
less than 130°F[TI-62-131].
9.ENSURE VCT pressure between 17 psig and 45 psig[PI-62-122].
ADJUST HIC-62-78A
to reduce VCT temperature
to less than 130°F.Page 11 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)10.CHECK RCP lower bearing and seal water temperature
less than 180°F: 11.GO TO appropriate
plant procedure.
----.---RESPONSE NOT OBTAINED IF any of the following conditions
met:*affected RCP lower bearing or seal water temperature
greater than 180°F OR*lower bearing and seal water temp indication
NOT available for affected RCP, THEN GO TO Step 1.___;11-.END OF SECTION Page 12 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow 1.CHECK#1 seal leakoff flow greater than 0.8 gpm per pump:*FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]2.CHECK#1 seal leakoff flow greater than 0.9 gpm per pump and NOT decreasing:
*FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]3.GO TO appropriate
plant procedure.
----.---4.ENSURE RCP seal water supply flow between 6 gpm and 10 gpm per pump:*FI-62-1A*FI-62-14A*FI-62-27A*FI-62-40A RESPONSE NOT OBTAINED GO TO Step 4.GO TO Step 4.IF seal water supply flow is less than 6 gpm AND CANNOT be restored, THEN ENSURE CCS supply to thermal barriers is less than 105°F:*TR-70-161[CCS HX 1A1(2A1)/1A2(2A2)
Outlet Temp]Page 13 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow (cont'd)5.CONTACT Engineering
for recommendations
WHILE continuing
with this procedure.
6.ENSURE VCT pressure between 17 psig and 45 psig[PI-62-122].
7.CHECK RCP standpipe level alarms DARK[M-5B, A-2, B-2, C-2, 0-2].RESPONSE NOT OBTAINED MONITOR the following:
a.RCOT parameters (O-L-2 AB, el.669)*Level, LI-77-1*Pressure, PI-77-2*Temperature, TI-77-21 b.Cntmt FI.&Eq.Sump Level rate of rise (ICS pt.U0969)Page 14 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow (cont'd)8.VERIFY RCP#2 seal leakoff less than or equal to 0.5 gpm USING Appendix A, RCDT Level Rate-of-Change.
9.MONITOR RCP lower bearing temperature
and seal water temperature
are stable and within limits (less than 225°F).RESPONSE NOT OBTAINED GO TO Section 2.4, RCP#2 Seal Leakoff High Flow.IF any of the following conditions
met:*affected RCP lower bearing temp or seal water temp rising uncontrolled
OR*affected RCP lower bearing temp or seal water temp greater than 225°F OR*affected RCP lower bearing temp and seal temp indication
NOT available THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]
Page 15 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow (cont'd)RESPONSE NOT OBTAINED CAUTION: NOTE: If low seal leakoff compensatory
actions are NOT successful, seal failure may result as indicated by a sudden increase in seal leakoff flow(greaterthan
8 gpm).Plant shutdown may be terminated
if Seal Leakoff flow stabilizes
at greater than 0.8 gpm with pump Lower Bearing temperature
and Seal Water Temperature
remaining stable (no indications
of seal failure).10.MONITOR RCP#1 sealleakoff
flow greater than 0.8 gpm:*FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]11.CHECK#1 seal leakoff flow greater than 0.9 gpm per pump and NOT decreasing:
*FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]INITIATE normal plant shutdown USING appropriate
plant procedures
AND STOP affected RCP within 8 hours.IF RCP#1 seal leakoff flow reverts to high leakage (greater than 8.0 gpm):*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]THEN GO TO Section 2.1 , RCP Tripped or Shutdown Required...GO TO Step 1...Page 16 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.3 Rep#1 Seal Leakoff Low Flow (cont'd)12.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.13.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational
Leakage 14.GO TO appropriate
plant procedure.
___111._---END OF SECTION Page 17 of 34 RESPONSE NOT OBTAINED
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.4 RCP#2 Seal Leakoff High Flow RESPONSE NOT OBTAINED NOTE: A leakoff of greater than 0.5 gpm indicates that a seal problem exists.1.NOTIFY Engineering
to consult with Westinghouse
for continued RCP operation as necessary.
2.CHECK RCP standpipe level alarm(s)LIT[M-5B, A-2, B-2, C-2, D-2].a.MONITOR RCOT parameters
at Radwaste Panel[Aux Bldg, 669'elev.]:*Level, LI-77-1*Pressure, PI-77-2*Temperature, TI-77-21 b.FILL affected RCP standpipe USING AR-M-5B, Annunciator
Response.*RCP 1[A-2]*RCP 2[B-2]*RCP 3[C-2]*RCP 4[0-2]c.IF RCP standpipe level alarm clears, THEN GO TO Section 2.5, RCP#3 Seal Leakoff High Flow.GO TO Step 3.Page 18 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.4 RCP#2 Seal Leakoff High Flow (cont'd)3.MONITOR RCP#2 seal INTACT:*VERIFY RCP#2 seal leakoff less than or equal to 0.5 gpm USING Appendix A, RCOT Level Rate-of-Change.
*VERIFY RCP vibration is within limits of annunciator
response 1-AR-M5-A (window 0-,3)VIBRATION&LOOSE PARTS MONITORING
ALM.*CONTACT Engineering
for recommendations.
RESPONSE NOT OBTAINED PERFORM the following within 8 hours: a.PERFORM normal plant shutdown USING appropriate
plant procedure.
b.WHEN reactor is shutdown or tripped, THEN STOP and LOCK OUT affected RCP.c.PULL TO DEFEAT affected loopT and T-avg:*XS-68-20*XS-68-2M (T-avg)Page 19 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.4 RCP#2 Seal Leakoff High Flow (cont'd)4.CHECK RCPs 1 and 2 RUNNING.5.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.6.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHotStandby
*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational
Leakage 7.GO TO appropriate
plant procedure.
--_l1li."'--
RESPONSE NOT OBTAINED CLOSE affected loop's pressurizer
spray valve.END OF SECTION Page 20 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.5 RCP#3 Seal Leakoff High Flow 1.CHECK RCP standpipe level alarms DARK[M-5B, A-2, B-2, C-2, 0-2].RESPONSE NOT OBTAINED PERFORM the following:
a.MONITOR Cntmt FI.&Eq.Sump Level rise rate (ICS pt.U0969)b.FILL affected RCP standpipe USING AR-M-5B, Annunciator
Response:*RCP 1[A-2]*RCP 2[B-2]*RCP 3[C-2]*RCP 4[0-2]c.IF RCP bearing temperature
rising, THEN GO TO Section 2.4, RCP#2 Seal Leakoff High Flow, Step 1.
Page 21 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.5 RCP#3 Seal Leakoff High Flow (cont'd)RESPONSE NOT OBTAINED NOTE: A leakoff rate of greater than 500 cc/hr indicates that a seal problem exists.The frequency and length of time filling the RCP standpipe may indicate the severity of the leak.2.MONITOR RCP#3 seal intact:*VERIFY RCP vibration is within limits of annunciator
response 1-AR-M5-A (window D-3)VIBRATION&LOOSE PARTS MONITORING
ALM.*CONTACT Engineering
for assistance
in determining
acceptable
leak rate for continued RCP operation.
3.CHECK RCPs 1 and 2 RUNNING.4.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.PERFORM the following within 8 hours: a.PERFORM non:nal plant shutdown USING appropriateplantprocedure.
b.WHEN reactor is shutdown or tripped, THEN STOP and LOCK OUT affected RCP.c.PULL TO DEFEAT affected loopT and T-avg:*XS-68-2D*XS-68-2M (T-avg)CLOSE affectedloop'spressurizer
spray valve.Page 22 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.5 Rep#3 Seal Leakoff High Flow (cont'd)5.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational
Leakage 6.GO TO appropriate
plant procedure.
----..---END OF SECTION Page 23 of 34 RESPONSE NOT OBTAINED
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.6 RCP Motor Stator Temperature
High RESPONSE NOT OBTAINED CAUTION: Operating the RCP with excess winding temperature
will reduce the expected life of the motor insulation.
NOTE: RCP motor winding temperature
limits are as follows:*329°F if RCS temperature
is less than 540°F.*311°F if RCS temperature
is greater than or equal to 540°F.1.MONITOR RCP Motor Stator temperature
less than applicable
limit by monitoring
the following computer points.:*Pump 1: T0409A, 411A or 412A*Pump 2: T0429A, 431A or 432A*Pump 3: T0449A, 451A or 452A*Pump 4: T0469A, 471A or 472A a.IF RCP Motor Stator temperature
reaches applicable
limit AND indication
is verified valid, THEN PERFORM the following:
1)IF reactor power greater than 10%, THEN INITIATE a plant shutdown at 2%per minute USING AOP-C.03, Emergency Shutdown.2)WHEN reactor power less than 10%, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]
Page 24 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED
RESPONSE 2.6 Rep Motor Stator Temperature
High (continued)
2.EVALUATE EPIP-1, Emergency Plan Initiating
Conditions
Matrix.3.EVALUATE the following Tech Specs for applicability:
*3.2.5, DNB Parameters
*3.4.1.1 , Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, ReS Operational
Leakage 4.GO TO appropriate
plant procedure.
----..---END OF SECTION Page 25 of 34 RESPONSE NOT OBTAINED
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 3.0 SYMPTOMS AND ENTRY CONDITIONS
3.1 Symptoms A.Any of the following annunciators
may indicate a RCP malfunction:
PANEL 0-XA-55-27-B-A, COMPONENT COOLING 0-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW 0-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW 0-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW 0-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 0-XA-55-27-B-E, COMPONENT COOLING/MiSe
0-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW 0-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW 0-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW 0-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 1(2)-XA-55-1B, AUXILIARY POWER/STATION
SERVICE A-1 6900V UNIT BO 1 (2)A TRANSFER A-2 6900V UNIT BO 1 (2)B TRANSFER A-3 6900V UNIT BO 1 (2)C TRANSFER A-4 6900V UNIT BO 1 (2)0 TRANSFER B-1 6900V UNIT BO 1 (2)A FAILURE OR UNOERVOLTAGE
B-2 6900V UNIT BO 1(2)B FAILURE OR UNOERVOLTAGE
B-3 6900V UNIT BO 1 (2)C FAILURE OR UNOERVOL TAGE B-4 6900V UNIT BO 1 (2)0 FAILURE OR UNOERVOL TAGE E-3 MOTOR TRIPOUTPNL1 (2)-M-1 THRU 1 (2)-M-6 Page 26 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 3.1 Symptoms (cont'd)PANEL XA-55-5A, REACTOR COOLANT-STM-FW A-6 TS-68-2M/N
REACTOR COOLANT LOOPS T AVG/AUCT T AVG OEVN HIGH-LOW B-5 CNTMT FLOOR&EQUIP DRAIN SUMP HI-HI-HI B-6 TS-68-2A1B
REACTOR COOLANT LOOPS L1 T OEVN HIGH-LOW 0-3 VIBRATION&LOOSE PARTS MONITOR ALARM PANEL XA-55-5B, evcs SEAL WATER AND RCP A-2 LS-62-6A REAC COOL PMP 1 STANDPIPE LVL HIGH-LOW A-3 FS-62-10 REAC COOL PMPS SEAL LEAKOFF LOW FLOW A-4 PdIS-62-96
SEAL WATER INJECTION FILTER HIGH L1P A-5 LS-68-10AlB
REAC COOL PMP 1 OIL RESERVOIR LEVEL HI-LOW B-2 LS-62-19A REAC COOL PMP 2 STANDPIPE LVL HIGH-LOW B-3 FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW B-4 PdIS-62-97
SEAL WATER INJECTION FILTER 2 HIGH L1P B-5 LS-68-34A1B
REAC COOL PMP 2 OIL RESERVOIR LEVEL HI-LOW C-2 LS-62-32A REAC COOL PMP 3 STANDPIPE LVL HIGH-LOW C-3 FS-62-1 REAC COOL PMPS SEAL WATER FLOW LOW C-5 LS-68-53A1B
REAC COOL PMP 3 OIL RESERVOIR LEVEL HI-LOW 0-2 LS-62-45A REAC COOL PMP 4 STANDPIPE LVL HIGH-LOW 0-3 PdS-62-8 REAC COOL PMPS SHAFT SEAL WATER L1P 0-5 LS-68-76A1B
REAC COOL PMP 4 OIL RESERVOIR LEVEL HI-LOW E-1 REAC COOL PMPS MOTOR STATOR TEMPERATURE
HIGH E-2 TS-62-42 REAC COOL PMPS LOWER BEARING TEMP HIGH E-3 REACTOR COOLANT PUMPS MOTOR THRUST BEARING TEMP HIGH E-4 TS-62-43 REAC COOL PMPS SEAL WATER TEMP HI E-5 FIS-62-12 RCP NO 1 SEAL BYPASS FLOW LOW Page 27 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 3.1 Symptoms (cont'd)PANEL XA-55-6A COMPONENT COOLING A-4 FS-68-6A REACTOR COOLANT LOOP 1 LOW FLOW B-4 FS-68-29A REACTOR COOLANT LOOP 2 LOW FLOW C-4 FS-68-48A REACTOR COOLANT LOOP 3 LOW FLOW 0-4 FS-68-71A REACTOR COOLANT LOOP 4 LOW FLOW E-4 RCP BUS UNDERFREQUENCY
I UNDERVOL TAGE B.Deviations
or unexpected
indication
on any of the following may indicate a RCP malfunction:
1.Erratic or abnormal RCP motor current 2.Erratic RCP motor frequency 3.Erratic or low RCS Loop Flow indications
4.Plant Computer RCP temperature
alarms 5.Indication
of high vibrations
on a RCP 6.Low RCP#1 seal LlP 7.High or low RCP#1 Seal leakoff flow 8.High or low RCP#1 Seal supply flow 9.Increasing
RCP#1 Seal temperature
10.Increasing
RCP lower bearing temperature
11.High VCT temperature
12.High VCT pressure 13.High VCT level 14.Increasing
Reactor Coolant Drain Tank level 15.High Containment
Floor&Equipment Sump Level rate of rise Page 28 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 3.1 Symptoms (cont'd)C.Any of the following automatic actions may indicate a RCP malfunction:
1.RCP trip from motor faults 2.Reactor Trip 3.Safety Injection 3.2 Entry Conditions
None END OF SECTION Page 29 of 34
SQN 4.0 REFERENCES
4.1 Performance
REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 A.EPIP-1, Emergency Plan Initiating
Conditions
Matrix B.E-O, Reactor Trip or Safety Injection C.AR-M-5B, Annunciator
Response 4.2 Technical Specifications
A.3.2.5, DNB Parameters
B.3.4.1.1, Reactor Coolant Loops and Coolant Circulation
-Startup and Power Operation C.3.4.1.2, Reactor Coolant System-Hot Standby D.3.4.1.3, Reactor Coolant System-Shutdown E.3.4.6.2, RCS Operational
Leakage Page 30 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 4.3 Plant Drawings A.47W600, Sheets 57,60 B.47W61 0-68, Sheets 1,2,3,4,6 C.47W61 0-77-3 D.47W61 0-62-2 E.47W61 0-72-1 F.47W61 0-74-1 G.47W61 0-63-1 H.47W61 0-67-1 I.47W61 0-3-3 J.47W61 0-70-1 K.47W61 0-30-2 L.47W61 0-47-1 M.47W61 0-82-1 N.45N765, Sheets 1, 2 O.45N724, Sheets 1, 2, 3, 4 P.45N751, Sheets 1, 2, 3,4, 5, 6, 7, 8 Q.45N732, Sheets 1, 2 4.4 10 CFR A.1 OCFR50, Appendix R Page 31 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
AOP-R.04 Rev.22 APPENOIXA Page 1 of 1 RCOT LEVEL RATE OF CHANGE CALCULATE RCDT level rate of change to obtain RCP#2 seal leakoff flowrate.FINAL VOLUME (gal)-INITIAL
VOLUME (gal)=LEVEL RATE OF CHANGE gpm L1 TIME (minutes)----Figure C.20 Page 1 of 1 REACTOR COOLANT DRAIN TANK LEVEL INDICATION
ON LI-77-1 t-100 Z 1LI 90 (J 0=: 80 LU 0-70..J 60 LLI 50>lIJ 40...I 0 30 LLI 20 J--(5 10-C 0 Z-/l-'V
V....v//'v.....v...,vI.'" l/VV l/i""l/ J'V\vl/l/.....v...... V:;/v l,,'v"\..",'""../'7,,-7-,,/N".'" ru"N.T RJ.NI i(/V"./V""...v....,..v".V./""-JI".../VOLUME*GALLONS 350 300 250 200 150 100 oj lso 10 GAL.INCREMENTS
NOTE: LEVEL TAP NOT AT TANK BOTTOM Page 32 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
APPENDIX B PAGE 1 of 1 RCPTRIPCRITERIA
AOP-R.04 Rev.22 Exceeding the following limitations
requires trip of the affected RCP, unless RCP operation is required by FR-C.1, Inadequate
Core Cooling or FR-C.2, Degraded Core Cooling[C.1]:*RCP#1 Seal less than 220 psid*RCP#1 Seal Temperature
greater than 225°F*RCP Lower Bearing Temperature
greater than 225°F*RCP Upper Motor Bearing Temperature
greater than 200°F*RCP Lower Motor Bearing Temperature
greater than 200°F*RCP Motor Voltage less than 5940V or greater than 7260V*RCP Motor Amps greater than 608 amps*RCP Vibration greater than 20 mils on any axis (x and/or y)[C.3]Page 33 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS
COMMITMENT
LIST AOP-R.04 Rev.22 COMMITMENT
ID C.1 C.2 C.3 SUMMARY OF COMMITMENT
Provide clear instructions
to the operators should any seal temperature, pressure, or leakage alarms annunciate.
Include conditions
for continued operation or immediate shutdown.Update procedural
guidance to conform to most recent Westinghouse
recommendations
on RCP shutdown with No.1 seal leakage outside the operating limits.Update procedural
guidance to include RCP vibration as a limitation.
Page 34 of 34 COMMITMENT
CORRESPONDENCE
NER 82-005 INPO SOER 81-007 INPO SOER 82-005 NER 930512001 Westinghouse
Tech Bulletin NSD-TB-93-01-R1
NER 970134001 TROIINPO SER 97-002
PREPAREDI REVISED BY: VALIDATED BY: APPROVED BY:*JPM B.1.c Page 1 of 11 Rev.0 SEQUOY AH NUCLEAR PLANT JOB PERFORMANCE
MEASURE B.1.c JPM WITHDRAW SHUTDOWN BANKS Datel Datel Datel (Operations
Training Manager)CONCURRED:
**(Operations
Representative)
Datel*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual
step changes that do not affect the flow of the JPM.**Operations
Concurrence
required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM B.1.c Page 2 of 11 Rev.0 NUCLEAR TRAINING REVISION/USAGE
LOG REVISION DESCRIPTION
OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 Modified JPM Y Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.
JPM B.1.c Page 3 of 11 Rev.0 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE
MEASURE Task: Withdraw Shutdown Banks JAITA task:#0010180101 (RO)Withdraw shutdown Banks KIA Ratings: 001 Control Rod Drive System A3 Ability to monitor automatic operation of the CRDS, including: (CFR: 41.7/45.13)
A3.05 Individual
vs.group rod position 3.5/3.5 Task Standard:1)Initiation
of withdrawal
of shutdown banks is initiated starting with Shutdown Bank A.2)Following failure of the group step counters, the reactor trip breakers are opened in accordance
with Technical Requirement
3.1.3.3.x Evaluation
Method: Simulator----In-Plant_===================================================================================
Performer:
Performance
Rating: SAT NAME UNSAT Performance
Time Start Time_Finish Time_Evaluator:
--------__-SIGNATURE DATE===================================================================================
COMMENTS
JPM B.1.c Page 4 of 11 Rev.0 SPECIAL INSTRUCTIONS
TO EVALUATOR:1.Sequenced steps identified
by an"s" 2.Any UNSAT requires comments 3.Place MODE 3 sign on the simulator.
4.This task is to be performed using the simulator in IC 183.If not available then raise boron to 1800ppm and withdraw rods to D@216;Trip reactor;Close Reactor trip breakers;Reset FWI and one MFPT, Stop TD AFW pump, and Reset M/D LCVs and stabilize SG levels.Place Rod Control Mode Selector Switch to the Manual position and rest startup switch.5.When the candidate withdraws Shutdown bank A approximately
100 steps, insert I/O Override/RD control rod drive system/Logical Output ZROSCSBAG1 (RESET)to ON to fail the Shutdown Bank A step counters to'0'6.Ensure operator performs the following required actions for SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.16 min Local-----Tools/Equipment/Procedures
Needed: 0-GO-2 0-GO-85-1 TR 3.1.3.3 AOP-C.01 TI-28 References:
Reference Title Rev No, 1.0-GO-2 Unit startup From Hot Standby to Reactor Critical 28 2.0-SO-85-1 Control Rod Drive System 33 3.TR 3.1.3.3 Reactivity
Control Systems, Position Indicating
13 System-Shutdown 4.AOP-C.01 Rod Control System Malfunctions
17 5.T1-28 Curve Book 215=============================================================================
READ TO OPERATOR Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Unit startup in progress following a trip from 100%powerdue to a generator electrical
relay malfunction.
2.Per TI-28, the shutdown banks fully withdrawn positon is 228 steps INITIATING
CUES: 1.You are to withdraw the shutdown banks in accordance
with 0-GO-2, Unit Startup From Hot Standby to Reactor Critical, Section 5.1, Step[26.2]2.Notify the SRO when the shutdown banks are fully withdrawn.
Job Performance
Checklist STEP/STANDARD
JPM B.1.c Page 5 of 11 Rev.0 SAT/U N SAT STEP 1.: Obtain the appropriate
procedure.
SAT UNSAT STANDARD: Operator identifies
0-SO-85-1 and goes to Section 6.3"Manual Operation of Rod Control System Below 15 Percent Power".STEP 2.:[1]ENSURE Section 5.2,Reset/CloseReactor
Trip Breakers has been completed.
STANDARD: Candidate determines
by looking at procedure that section 5.2 is complete.COMMENTS: STEP 3.:[2]IF the shutdown and control rods were withdrawn 5 steps to prevent thermal lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawal.
Cue: If asked"Rods were not withdrawn 5 steps" STANDARD: Candidate N/As the step.COMMENTS: STEP 4.:[3]MOMENTARILY
PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System.STANDARD: Candidate places Rod control Startup Step Counter Reset, 1-SUS, to startup and then releases switch.COMMENTS: Start Time__SAT_UNSAT SAT_UNSAT SAT UNSAT
Job Performance
Checklist STEP/STANDARD
JPM B.1.c Page 6 of 11 Rev.a SAT/UNSAT STEP 5.:[4]ENSURE all Full Length Rod step counters reset to zero.-SAT-UNSAT STANDARD: Candidate verifies all 14stepcounters
are reading'000'COMMENTS: STEP 6.:[5]VERIFY rod control IN-OUT direction lights are NOT LIT.-SAT-UNSAT STANDARD: Candidate verifies that both the RODS IN and the RODS OUT lights are not lit on 1-M-4.COMMENTS: STEP 7.:[6]DEPRESS[RCAS], Rod Urgent Failure Alarm Reset.-SAT-UNSAT STANDARD: Candidate pushes Rod Urgent Failure Alarm Reset, 1-RCAS COMMENTS: STEP 8.:[7]RESET Window 6 (A-6), ROD CONTROL SYSTEM URGENT-SAT FAILURE alarm on panel[XA-55-4B]
using[XS-55-4A], UNSAT Annunciator
RESET/ACKITEST
Switch.-STANDARD: Candidate resets the ROD CONTROL SYSTEM URGENT FAILURE alarm using 1-XS-55-4A
if lit.COMMENTS:
Job Performance
Checklist STEP/STANDARD
JPM 8.1.c Page 7 of 11 Rev.0 SAT/UNSAT[8]VERIFY the following rod control system alarms on panel[XA-55-4B]
are NOT LIT: STEP 9.::WfNOOW NitlMBER NOT LITSAT UNSAT STANDARD: Candidate verifies listed windows on 1-M-4 overhead annunciatot55-48 are not lit COMMENTS: STEP 10.:[9]ENSURE Plant computer points for rod bank position are ZERO using the following computer points: SAT UNSAT o o o o o o o o Cue: After candidate demonstrates
ability to access computer points'All listed points have been verified to be'0'.STANDARD: Candidate verifies listed computer points are reading'0'on ICS.There are several methods/screens
to access the points COMMENTS:
Job Performance
Checklist STEP/STANDARD
JPM B.1.c Page 8 of 11 Rev.0 SAT/UNSAT STEP 11.:[10]MONITOR Control Rod position USING Rod Position Indicators
-SAT ICS screen 30 minute trend during SO&Control Banks UNSAT withdrawal
to aid in detecting rod misalignment.
-STANDARD: Candidate locates the Rod Position Indicator RPI TREND screen on the ICS.(when on RPI screen, the RPI TREND screen can be accessed via clicking on TREND.)COMMENTS: STEP 12.:[11]IF Individual
Rod Position Indication
does not indicate proper rod-SAT position during withdrawal
of SO Banks, THEN UNSAT[a]STOP rod withdrawal.
-[b]ENSURE subcriticality.
[c]CONTACT MIG AND INITIATE troubleshooting.
[d]IF troubleshooting
does not resolve the problem, OR subcriticality
can NOT be verified, THEN INITIATE Reactor TRIP.STANDARD: Candidate acknowledges
the requirement
of the IF/THEN step for individual
RPls.No action required.STEP 13.:[12]IF Individual
Rod Position Indication
does not indicate proper rod-SAT position during withdrawal
of Control Banks, THEN UNSAT GO TO AOP-C.01 section 2.6 Rod Position Indicator (RPI)-Malfunction
-Modes 1 or 2.STANDARD: Candidate acknowledges
the step, realizes it refers to control banks, and No action is required for this task of withdrawing
shutdown banks COMMENTS:
Job Performance
Checklist STEP/ST AN DARD JPM B.1.c Page 9 of 11 Rev.0 SAT/UNSAT STEP 14.:[13]PLACE[HS-85-5110], Rod Control Mode Selector to the SBA-SAT position.UNSAT-STANDARD: Candidate rotates Mode Control Mode Selector, 1-HS-85-511
0, counterclockwise
to the SBA position Critical Step COMMENTS: STEP 15.:[14]VERIFY Rod Speed Indicator[51-412], indicates-SAT 64 Steps/minute.
UNSAT-STANDARD: Candidate determines
SI-412, Rod Speed, on 1-M-4 vertical panel is reading 64 steps/min COMMENTS: STEP 16.:[15]ENSURE Shutdown Bank A demand position counters-SAT operational
by performing
the following:
[C.2]UNSAT[a]BUMP[HS-85-5111], Rod Control Switch to withdraw-Shutdown Bank A one-half step at a time, for one full step.[b]CHECK group demand position counters advance properly.[c]BUMP[HS-85-5111]
to withdraw Shutdown Bank A one-half step at a time, for the second full step.[d]VERIFY group demand position counters advance properly.[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
B.INITIATE WO to have counter repaired.C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank A fully INSERTED.2.RETURN to beginning of this step.STANDARD: Candidate uses Rod Control, 1-HS-85-5111, IN-OUT switch to withdraw SBA rods 2 steps in 12 step increments
while checking the group step counters are operating properly.COMMENTS:
Job Performance
Checklist STEP/STANDARD
Note to evaluator:
The shutdown bank full out position is stated in the initial conditions, if candidate refers to TI-28 provide a cue that the full out position is 228 steps.STEP 17.:[16]WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN position using[HS-8S-S111].
Cue: If candidate initiates use of TI-28 to determine full out position, state"The full out position is 228 steps." STANDARD: Candidate uses Rod Control, 1-HS-85-5111, IN-OUT switch on 1-M-4 to withdraw SBA COMMENTS: Note to evaluator:
Malfunction
to fail step counters is to be inserted when the rods reach approximately
100 steps.Candidate may refer to TR-3.1.3.3.
If so the required action is to open the Reactor Trip breakers.STEP 18.: Open the Reactor Trip Breakers Cue: After the reactor trip breakers have been opened state'We will stop here" STANDARD: Candidate determines
the Group 1 step counter is not capable of determining
the demand position for each of the Shutdown bank a rods within2 steps and opens the reactor trip breakers.COMMENTS: JPM B.1.c Page 10 of 11 Rev.0 SAT/UNSAT SAT UNSAT Critical Step SAT UNSAT Critical Step Stop Time__
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION
OF TASK)DIRECTIONTOTRAINEE:
I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating
cues and reports on other actions when directed by you.Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Unit startup in progress following a trip from 1000/0 power due to a generator electrical
relay malfunction.
2.Per TI-28, the shutdown banks fully withdrawn positon is 228 steps INITIATING
CUES: 1.You are to withdraw the shutdown banks in accordance
with 0-GO-2, Unit Startup From Hot Standby to Reactor Critical, Section 5.1, Step[26.2]2.Notify the SRO when the shutdown banks are fully withdrawn.
Sequoyah Nuclear Plant Unit 0 General Operating Instructions
O-GO-2 UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL Revision 0028 Quality Related Level of Use: Conti"nuous
Use Effective Date: 10-31-2007
Responsible
Organization:
OPS, Operations
Prepared By: D.A.Porter Approved By: W.T.Leary Current Revision Description
Revised Section 5.1 steps[28]and[29]to clarify applicability
of Sect.5.2 and 5.3.Added Sect.5.2 step[67].Modified title of Sect.5.2 and 5.3.Added limitation
associated
with minimum temp for criticality.
Provided more specific guidance on S/G level control in Sect.4.0 Step[7].THIS PROCEDURE IMPACTS REACTIVITY
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 2 of 85 Table of Contents 1.0 FI*RST SECT.ION 3 1.*1 Purpose: 3 1.2 Scope 3 2.0 REFERENCES
3 2.1 Performance
References
3 2.2 Developmental
References
5 3.0 PRECAUTIONS
AND LIMITATIONS
...........................................*...............................
6 3.1 PRECAUTIONS
6 3.2 LIMITATIONS
8 4.0 PREREQUiSiTES
......................*..........................9 5.0 INSTRUCTIONS
12 5.1 Actions to be performed prior to a reactor startup 12 5.2 Reactor Startup with Low Power Physics Testing 21 5.3 Reactor Startup without Physics Testing 45 6.0 RECORDS 69 A*ppendix A: DELETED70 Appendix B: MODE 3 TO MODE 2, 1 REVIEW AND APPROVAL 71 Appendix C: DETERMINING
SOURCE RANGE COUNT RATE DOUBLING 79 Appendix D: ACTIONS IF REACTOR STARTUP MUST BE ABORTED 80, Appendix E: ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY
81 Source Notes 83 ATTACHMENTS
Attachment
1: UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 70f 85 3.1 PRECAUTIONS (continued)
2.During Rod Movement a.Ensure RO has peer check b.EnsureRO is following procedure c.EnsureRO understands
criteria for stopping rod motion (based upon number of steps and/or nuclear instrument
response)d.Watch performance*
of rod manipulation
while listening to audible indication
of rod.step e.Ensure peer checking meets expectations (OPDP-1)f.Re-verifyitems
of initial evaluation (on previous page)g.Monitor plant for expected response
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 8of8S 3.2 LIMITATIONS
A.Simultaneous
reactivity
addition by rod withdrawal
and dilution is NOT allowed while in the source range.B.If at any point during the approach to criticality, ONE of the two source range detectors shows an unexplained
increase in count rate equal to or greater than a factor of 5, or if BOTH source range detectors show an unexplained
increase in count rate equal to or greater than a factor of 2, the approach to criticality
shall be SUSPEN*DED
IMMEDIATELY (Le., all rod withdrawals
and/or boron dilutions shall be terminated).
Further positive reactivity
changes shall not be resumed until an evaluation
is performed and the Shift Manager authorizes
a resumption
in the approach to criticality.
C.After refueling operations, the NIS indications
may be inaccurate
until calibration
at higher power levels.The NIS calibration
procedures
will adjust the PRM trip set points to ensure that the excore detectors do not contribute
to an overpower condition.
Prior to startup, the PRM high range flux trip setpoint will be adjusted from 109 to 60%, with the rod stop (C-2)remaining at 103%.[C.3]D.While in Mode 3, maintain the Reactor Coolant System boron concentration
in accordance
with 0-SI-NUC-000-038.0, Shutdown Margin requirements.
E.The stepping or tripping of the.Control Rod during periods when coolant crud level are high should be kept to a minimum.This will limit the possibility
of CRDMmis-stepping
due to crud contamination
of CRDM latch assemblies.
F.The lowest operating loop temperature (T-avg)shall be greater than or equal to 541°F (LCO 3.1.1.4, Minimum Temperature
for Criticality).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 9 of 85 4.0 STARTUP No.---PREREQUISITES
Unit---NOTES1)Throughout
this Instruction
where an IFITHEN statement exists, the step should be N/A'd if the condition does not exist.2)Prerequisites
may be completed in any order.3)Management
oversight is required for a Reactor Startup after a non-refueling
outage.A Reactor Startup after a refueling outage is a CIPTE.[1]ENSURE Instruction
to be used is the latest copy of effective version.t v 1A[2]REVIEW Precautions
and Limitations.
[3]INDICATE below which instruction
this GO is being entered from:*0-GO-1 (cold shutdown to hot standby)*0-GO-6 (30%reactor power to hot standby)*0-GO-7 (hot standby to cold shutdown)*0-GO-5 (normal power operation)
[4]MAINTAIN pressurizer
pressure within the normal operating band by use of the pressurizer
heaters and spray valves.o o o[5]MAINTAIN pressurizer
level greater than or equal to 25%.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 10 of8S 4.0 STARTUP No.---PREREQUISITES (continued)
Unit-i-NOTE Due to instru*ment
inaccuracies
the steam dump or SG atmospheric
relief valve setpoint of 84%or 1005 psig maybe+/-1%or+/-12 psig off.[6]MAINTAIN T AVG stable at approximately
547°F with steam dumps in pressure mode or with SG atmospheric
relief valves.NOTE Minor S/G level variations
which exceed the plus or minus 7%band should not be considered
a procedural
violation.
[7][8][9]MAINTAIN steady-state
S/G levels at approximately
33%(plus or minus 7%)using Auxiliary Feedwater.
ENSURE all reactor coolant pumps are in operation in accordance
with 1,2-S0-68-2, Reactor Coolant Pumps.[C.12]IF the reactor vessel head has been removed, THEN ENSURE conditional
performance
of 0-SI-SXX-085-043.0, Rod Drop Time Measurements, has been performed to comply with SR 4.1.3.4.a.
[10]REQUEST Periodic Test Coordinate
to confirm that the following checklists
have been distributed:
.[10.1]Mode 3 to Mode 2, 1, Surveillance
Checklist (NA if previously
performed for this startup).[10.2]Reactor Trip Breaker Checklist (NA if previously
performed for this startup).[11]ENSURE East Valve Vault Room Vent Chute dampers OPEN.(inside door near SPING Room, Ref.PER 03-002446-000).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 11 of 85
4.0 STARTUP No.---PREREQUISITES
.(continued)
[12]NOTIFY MIGto
LR-3-43A and LR-3-98A, Steam Generator Wide Range Level Recorders, to 80 0/0-90 0/0.[13]E*NSURE each performer documents their name and initials: Date L!l
I Print Name Initials Print Name InitialsAbbot fA°Jk\L 6..!END OF TEXT
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 12 of 85 5.0 STARTUP No.---INSTRUCTIONS
Unit
5.1 Actions to be performed prior to a reactor startup[1]ENSURE Section 4.0, Prerequisites
complete.WItt NOTE Steps 5.1[2]through 5.1[11]may be performed in any order.[2]INTIATE Appendix B, , Mode 3 to Mode 2,1 Review And Approval while continuing
with this instruction.
[3]OBTAIN assistance
from Systems Engineering
to complete Appendix B steps associated
with Pressurizer
Spray line bypass valves.NOTE Steps for MFPT startup maybe performed in parallel with other activities.
The MFPT trip busses shall be energized prior to entering Mod'e 2 (LeO 3.3.2.1 or 3.3.2)except as allowed by LCO 3.0.4.[C.1][4]INITIATE applicable
section(s)
of 1, 2-S0-2/3-1
to prepare at least one MFP for startup, while continuing
with this instruction.(N/Aif no MFPT available)
[5]ENSURE TDAFW LCVs are in NORMAL.y/1A 1st
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 13 of 85 STARTUP No.Unit+-Date 5.1 Actions to be performed prior to a reactor startup (continued)
CAUTION Rapid changes in pressurizer
enclosure temperature
may result in pressurizer
safety valve simmer.[6]IF lower compartment
coolers are not in service, THEN[6.1][6.2]ALIGN lower compartment
coolers to maintain pressurizer
enclosure temperature
less than 11 oaF in accordance
withO-SO-30-5.
MONITOR Pressurizer
enclosure temperature
using Plant Computer pt.T1001A.[7]IF control roddrivecoolers
are not in service, THEN[7.1][7.2]ALIGN control rod drive coolers to maintain shroud enclosure temperature
less than 164°F in accordance
with 0-SO-30-6.
MONITOR Reactor Cavity Air temperature
using Plant Computer pt.T1014A.NOTE New analysis is not required for this startup.Routine analysis is sufficient
unless there is reason to suspect che.mistry
has been changed.[8]NOTIFY Chemistry Supervisor
that mode change from 3 to 2 requires sampling in accordance
with O-SI-CEM-OOO-050.0,
.2, and O-SI-CEM-030-415.0
requirements.
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 14 of 85 5.1 STARTUP No.Unit 4-
to be performed prior to a reactor startup (continued)
Date 0 llxI I NOTE To preserve the life of 20 AST and 20*ET, power must be removed from turbine trip bus A and trip bus B if unit startup is extended.[9]ENERGIZE main turbine trip buses by CLOSING the following breakers (NA breakers not applicable):
UNIT TRAIN BREAKER 250V DC POSITION INITIALS WIll TRAINA 1-BKRD-47-KA/516 BATT Bd 1 CLOSED 1st 1TRAINB 1-BKRD-47-KB/516 BATT Bd 2 CLOSED 1 st lJ/l{)TRAIN A 2-BKRD-47-KA/519 BATT Bd 1 CLOSED 1st 2 i,vf If TRAIN B 2-BKRD-47-KB/519
BATT Bd 2 CLOSED 1st NOTE Step 5.1[10]may be marked N/A if not required.[10]PERFORM 0-PI-OPS-047-723.0, 20IAST, 201ET, 20-110PC, and 20-210PC Operability
Verification (N/A if not performed).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 15 of 85 5.1 Actions to be performed prior to a reactor startup (continued)
STARTUP No.---Unit 1 CAUTION Operation of the EHCpumps without the turbine being reset will result in overheating
of the EHC fluid and"pumps.NOTE Startup of EHC and turbine reset"may be postponed until later in startup.(N/Aif postponed)
oj/if-LuiII Date[11][12][13]ENSURE EHC system in service in accordance
with 1,2-80-47-2 (NA if previously
performed).
IFno MFPT is ready for start up per 1,2-80-2/3-1, THEN GO TO Section 5.1[18].ENSURE MFPT designated
for startup has been tested and ready for start up per 1, 2-80-2/3-1
PRIOR to proceeding
with the next step.U/1{)Initials
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 16 of 85 STARTUP No.Unit--1-Date
5.1 Actions to be performed prior to a reactor startup (continued)
NOTES 1)Steps for MFPT startup may be performed in parallel with other activities.
The MFPT trip busses shall be energized prior to entering Mode 2 (LCO 3.3.2.1 or 3.3.2)except as allowed by LeO 3.0.4.[C.1]2)Power is placed on only ONE MFPT trip bus in Step 5.1[14]to prevent inadvertent
AFWP start.[14]ENSURE power restored to ONLY ONE of MFPT tri.p busses on the applicable
unit: (N/A breakers not applicable.)
[C.1]ELECTRICAL
BREAKER INITIALS PUMP BREAKER NO.BOARD POSITION 250v DC MFPT 1A 1-BKRD-46-KA/523
Battery Bd I CLOSED 1st CV 250v DC 0'iA-MFPT 18 1-BKRD-46-KA/524
Battery Bd I CLOSED 1st 250v DC MFPT 2A 2-BKRD-46-KB/523
Battery Bd 2 CLOSED 1st CV 250v DC MFPT 28 2-BKRD-46-KB/524
Battery Bd 2 CLOSED 1st CV
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 I TO REACTOR CRITICAL Rev.0028 Page 17 of 85 STARTUP No.Unit--l-Date 5.1 Actions to be performed prior to a reactor startup (continued)
CAUTION Failure to reset a MFPT prior to energizing
the remai"ning
MFPT trip buss will initiate an ESF actuation.
NOTE If 81 signal or Hi/Hi steam generator level has occurred, Reactor Trip Breakers will have to be cycled.[15]RESET MFPT energized in step 5.1[14]above.vV1A 1st o&4f tJ
Time ate 0041 6\/j{/oJ Time Date NOTE IF the remaining NON-running
MFPT is not available, THENN/A step 5.1[16]and 5.1[17][16]RESTORE power to remaining MFPT Trip Bus on applicable
unit.(N/A breakers not applicable)
PUMP BREAKER NO.ELECTRICAL
BREAKER INITIALS BOARD POSITI"ON 250v DC Battery MFPT 1A 1-BKRD-"46-KA/523
Bd I CLOSED 18t CV 250v"DC Battery MFPT 1B 1-BKRD-46-KA/524
Bdl CLOSED 1st CV 250v DC Battery MFPT 2A 2-BKRD-46-KB/523
Bd 2 CLOSED 1st CV 250v DC Battery MFPT 28 2-BKRD-46-KB/524
Bd 2 CLOSED 1st CV
SQN UNIT STARTUP FROM.HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 18 of 85 5.1 STARTUP No.
Actions to be performed prior to a reactor startup (continued)
[17]RESET MFPT energized in step 5.1[16]above.1 st CV Time Time Date Date[18]SELECT one source range channel and one intermediate
range channel with the highest readings to record on NR 45.[19]ENSURE audio count rate channel isin operation and selected for source range channel with highest reading.[C.11][20]ENSURE all reactor first out alarms reset.NOTE Refer to 1-PI-OPS-000-021.1 (Unit 1)or 2-PI-OPS-000-023.1 (Unit 2)for updating the Plant Computer.[21]IF ICS is available, THEN ENSURE Plant Computer is reset and updating (NA if previously
performed).
[C.S]NOTE Closing of the RTB's for performance
of O-SI-OPS-085-011.0 (SR4.1.3.3)
is addressed in Licensing and NRC TelephoneNisit
Report RIMs#S10 960521 800.[22]IF
is out-of-frequency, THEN[22.1]CLOSE RTB's provided Group Demand counters have no known deficiencies.
[22.2]PERFORM 0-SI-OPS-085-011.0 (NA if above step cannot be performed).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 19 of 85 STARTUP No.Unit-L Date5.1 Actions to be performed prior to a reactor startup (continued)
[23]IF control rods were withdrawn 5 steps to prevent thermal lockup during ReS heatup, THEN INSERT control rods in accordance
with 0-SO-85-1.
[24]ENSURE Rod Bank Update completed by performing
the following:
[24.1]DEPRESS NSSS and BOP button on ICS main screen.if[24.2]DEPRESS-ROD BANK UPDATE Button AND ENSURE all bank positions are zero.GV'[24.3]DEPRESS F3 to save these rod bank positions.
UV NOTE TI-28 defines fully withdrawn position.[26]IF shutdown rods are inserted, THEN PERFORM the following:
[26.1]VERIFY sufficient
shutdown reactivity
exists USING 0-SI-NUC-000-038.0, Shutdown Margin.[26.2]WITHDRAW Shutdown Rods to fully withdrawn position in accordance
with 0-SO-85-1.
1st CV
SQN UNIT STARTUP FROM HO'T STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 20 of 85 STARTUP No.Unit Date5.1 Actions to be performed prior to a reactor startup (continued)
[27]CONDUCT a pre-evolution
briefing, stressing the following points:*Management
Expectations
*Limitations/Precautions
*Avoid activities
which distract the operators[SQ990136PERJ
*Appropriate
Contingencies
*Communications
*Chain of Command*Requirements
for conservative
actions and strict compliance
with written procedures
when repositioning
control rods.[C.11]SRO[28]IF this start up is after a refueling outage AND Low Power Physics Testing has NOT been performed, THEN[28.1]VERIFY applicable
actions in Section 5.1 completed or initiated.
[28.2]GO TO Section 5.2.[29]IF this start up is after a non-refueling
outage OR Low Power Physics Testing has already been completed, THEN[29.1]VERIFY applicable
actions in Section 5.1 completed or initiated.
[29.2]GO TO Section 5.3.[30]IF unit is to be shutdown, THEN GO TO 0-GO-7, Unit Shutdown from Hot Standby to Cold shutdown.END OF TEXT
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 21 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing[1]VERIFY applicable
actions in Section 5.1 completed or initiated.
Date---NOTE Steps 5.2[2]through 5.2[9]may be performed out of sequence.[2]IF anyMFPT trip buss is NOT energized, THEN[2.1]ENSURE requirements
of LCO 3.0.4 are satisfied.
[2.2]NOTIFY UnitSRO that LCO 3.3.2.1 (3.3.2)action 20 will apply when Mode 2 is entered.[3]ENSURE Appendix B, Mode 3 to Mode 2, 1 Review and Approval has been completed to ensure all restraints
to Mode 2, 1 entry have been resolved and approvals for mode change granted.[4]BLOCK the Source Range High Flux At Shutdown alarm:[4.1]PLACE both HI FLUX AT SHUTDOWN switches on panel M-13 to BLOCK position.[4.2]VERIFY annunciator
XA-55-4B, window C-1, SOURCE RANGE HIGH SHUTDOWN FLUX ALARM is LIT.[C.2]BLOCK SM o[5]VERIFY greater than or equal to 0.5 cps on highest reading SR instrument.
o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 22 of 85 STARTUP No.Unit Date----5.2 Reactor Startup with Low Power Physics Testing (continued)
NOTE The following count rates may be used as a reference during the approach to criticality.
[6]RECORD SR count rates from two of the following:
[C.2](NIA instruments
not used) (N31)cps XI-92-5002A (N32)cps OR XI-92-5001
B XI-92-5002B (N31)(N32)CAUTION___cps___cps Date Time After refueling, NIS indications
may be inaccurate
until calibration
at higher power levels.Therefore, NIS calibration
procedures
will reduce PRM trip setpoints from 109 to 60%to ensure that excore detectors do NOT contribute
to an overpower condition.(Rod Stop will remain at 103%).ReS loop!:l T indicators
should" be used for power indication
below 30%.[7]ENSURE Power Range high flux trip setpoints reduced to 60%in accordance
with following:
[C.3]*1,2-SI-ICC-092-N41.1
0*1,2-SI-ICC-092-N42.2
0*1,2-SI-ICC-092-N43.3
0*1,2-SI-ICC-092-N44.4
0 Instrument
Maintenance
Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 23 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
[8]ENSURE PRM calibration
values set to startup values.[C.3]Date----Reactor Engineer Time Date NOTE O-RT-NUC-OOO-003.0, Low Power Physics Testing is performed by RxEngineering
concurrently
with this procedure.
[9]RECORD estimated critical position calculated
in accordance
with 0-RT-NUC-OOO-003.0, Low Power Physics Testing.Estimated critical position: Boron concentration:
steps on bank ppm Initials Time Date[10]VERIFY Steps 5.2[1]through 5.2[9]completed.
[11]IF actual RCS boron concentration
does NOT approximately
equal estimated critical boron concentration
determined
in O-RT-NUC-OOO-003.0, THEN[11.1]DETERMINE the appropriate
boration/dilution
requirements
to achieve estimated boron conc.0[11.2]DILUTE/BORATE
in accordance
withO-SO-62-7
to the estimated critical boron concentration.
[C.12]0[11.3]OPERA TE pressurizer
heaters/spray
as necessary to equalize boron concentration (within 50 ppm)between reactor coolant loops and the pressurizer.
[C.12]0[11.4]WHEN sufficient
mixing has occurred, THEN OBTAIN a new boron sample.0[11.5]ENSURE actual boron concentration
is approximately
equal to the estimated critical boron concentration.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 24 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
Date----[12]RECORD minimum and maximum rod positions corresponding
to+/-1000 pcm ALLOWABLE LIMITS (Tech Spec Limit)determined
by 0-SI-NUC-000-001.0, Estimated Critical Conditions.
[C.11]Minimum allowable rod position Maximum allowable rod position steps on bank steps on bank Initials Time Date[13]VERIFY all shutdown rods are fully withdrawn in accordance
with O-SI-OPS-OOO-004.0, Surveillance
Requirements
Performed on Increased Frequency with no Specific Frequency, within 15 minutes prior to withdrawing
control rods.Time NOTE SR 4.1.1.4.a required verifying lowest T-avggreater
than or equal to 541°F within 15 minutes prior to achieving criticality.
[14]IF 0-SI-SXX-068-127.0
is NOT in progress, THEN INITIATE applicable
sections of 0-SI-SXX-068-127.0
to satisfy SR 4.1.1.4.a., Minimum Temperature
For Criticality.
Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 25 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
Date----[15]NOTIFY onsite personnel of reactor startup over PIA system.0 CAUTION Avoid operations
that could produce sudden changes of temperature
or unplanned boron-concentration
changes during approach to criticality
or low power.NOTES1)Nuclear instrumentation
shall be monitored very closely for indications
of unplanned reactivity
rate of change.[C.11]2)Activities
that can distract operators and supervisors
involved with reactor startup, such as shift turnover and surveillance
testing during approach to criticality, SHALL BE avoided.[C.12]3)ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for monitoring
NIS indications.
[16]MONITOR nuclear instruments
during approach to criticality:
[16.1]MONITOR source range and intermediate
range NIS to identify potential reactivity
anomalies.
[C.11][16.2]IF desired to place NR-45 recorder in fast speed, THEN ADJUST chart speed to high.D
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 26 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)
CAUTION Do NOT exceed a steady startup rate of+1 DPM.NOTE The unit enters Mode 2 when the control banks are first withdrawn.
[17]INITIATE a reactor startup by performing
the following:
[17.1]RECORD both source range readings for ICRR base counts.N-31 CPS---.--.-N-32 CPS---Initials[17.2]RECORD intermediate
range readings.N-35 0/0---N-36 0/0---Initials[17.3]CALCULATE initial source range count doubling value USING Appendix C.MODE 2[17.4]INITIATE withdrawal
of control banks in accordance
with 0-80-85-1 to first stop point: CONTROL BANK A 128 STEPS[17.5]ENSURE Mode 2 entry is logged (log entry may be performed out of sequence later).o
SQN*UNIT STARTUP FROM HOT STANDBY O-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 27 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
[18]WHEN control bank A is at 128 steps, THEN PERFORM the following:
[18.1]STOP rod withdrawal.
[18.2]WAIT for approximately
two minutes.[18.3]NOTIFYRx Engineering
to perform ICRR calculation
in accordance
with
[C.11]CAUTION Date---Lowest loop T-avg must be verified greater than or equal to 541°F
15 minutes prior to achieving criticality.
NOTES1)Approximately
five to seven count doublings are expected to result in criticality.
However, criticality
should be anticipated
at any time.2)Proper bank overlap must be verified using 0-80-85-1 as each successive
rod bank is withdrawn.
[19]WHEN concurrence
obtained from Rx Engineering, THEN INITIATE rod withdrawal
to first count doubling (determined
in App.C)USING 0-80-85-1.
o
SQNUNITSTARTUP
FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 28 of 85 STARTUP No.Unit Date------5.2 Reactor Startup with Low Power Physics Testing (continued)
NOTE Steps 5.2[20]and 5.2[21]may be repeated as necessary if rod motion is stopped prior to reaching doubling value.[20]WHEN any of the following conditions
are met:*Source range count rate is approximately
equal to first doubling value determined
in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)
OR*Operators orRx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[21]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor
concurrence
is o*btained to resume, THEN RESUME rod withdrawal
to first count doubling USING 0-80-85-1.
[22]IF source range count rate has reached or exceeded first doubling, THEN PERFORM the following:
[22.1]ENSURE rod motion STOPPED.[22.2]WAIT approximately
2-3*minutes to allow count rate to rise.DODD DODD[22.3]NOTIFY Rx Engineering
to perform leRR calculations
in accordance
with 0-RT-NUC-000-003.0.
[C.11]0[22.4]DETERMINE new count doubling range USING Appendix C.
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 29 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing-(continued)
[23]IF ICRR plot indicates criticality
will fall outside+/-1000 pcm ECC termination
band, THEN[23.1]NOTIFY SM and OutyPlant Manager.
EVALUATE if ECC should be recalculated
prior to continuing
startup.[23.3]IF startup must be aborted, THEN PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted.D[24]WHEN concurrence
obtained from Rx Engineering, THEN INITIATE rod withdrawal
to second doubling range (determined
in App.C)USING 0-SO-85-1.
NOTE Steps 5.2[25]and-5.2[26]may be repeated as n-ecessary
if rod motion is stopped prior to reaching doubling range.[25]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds second doubling range determined-in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)
OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.D DODD
DODD SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 30 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)
[26]IF rod motion was stopped prior to reaching doubling ra"nge AND Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
to second doubling range USING 0-SO-85-1.
[27]IF source range count rate has reached or exceeded second doubling range, THEN PERFORM the following:
[27.1]ENSURE rod motion STOPPED.[27.2]WAIT approximately
2-3 minutes to allow count rate to rise.[27.3]NOTIFY Rx Engineering
to perform ICRR calculations
in accordance
with 0-RT-NUC-000-003.0.
[C.11]0[27.4]DETERMINE new count doubling range USING Appendix C.[28]IF ICRR plot indicates criticality
will fall outside+/-1000 pcm ECC termination
band, THEN[28.1]NOTIFY SM and Duty Plant Manager.[28.2]EVALUATE if EGG should be recalculated
prior to continuing
startup.[28.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.D[29]IF leRR plot trend indicates acceptable
EGC, THEN INITIATE rod withdrawal
to third doubling range (determined
in App.G)USING 0-80-85-1.
D
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 31 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
Date----NOTE Steps 5.2[30]and 5.2[31]may be repeated as necessary if rod motion is stopped prior to reaching doubling range.[30]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds third doubling range determined
in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)
OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[31]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor
concurrence
is obtaine*d to resume, THEN RESUME rod withdrawal
to third doubling range USINGO-SO-85-1.
[32]IF source range count rate has reached or exceeded third doubling range, THEN PERFORM the following:
[32.1]ENSURE rod motion STOPPED.[32.2]WA*IT approximately
2-3 minutes to allow count rate to rise.DODO DODD[32.3]NOTIFYRx Engineering
to perform leRR calculations
in accordance
with 0-RT-NUC-000-003.0.
[C.11]0[32.4]DETERMINE new count doubling range USING Appendix C.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 32 of 85[33.1]NOTIFY SM and Duty Plant Manager.[33.2]EVALUATE if EGG should be recalculated
prior to continuing
startup.[33.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[34]IF ICRR plot trend indicates acceptable
ECG, THEN INITIATE rod withdrawal
USING 0-SO-85-1 to fourth doubling range (App.G)or criticality.
NOTE Steps 5.2[35]through 5.2[37]may be repeated as necessary if rod motion is stop*ped prior to reaching doubling range or criticality.
[35]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds fourth doubling range determined
in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)
OR*Bank D rods reach fully withdrawn position OR D*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.DODD
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 33 of 85 STARTUP No.Unit Date----5.2.Reactor Startup with Low Power Physics Testing (continued)
[36]IF reactor is critical, THEN GO TO Step 5.2[59](N/A Steps 5.2[37]through 5.2[58]).[37]IF ALL of the following conditions
are met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank D rods are below fully withdrawn position*Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
USING 0-SO-85-1 to fourth doubling range or criticality (whichever
comes first).[38]IF source range count rate has reached or exceeded fourth doubling range, THEN PERFORM the following:
[38.1]ENSURE rod motion STOPPED.[38.2]WAIT approximately
2-3 minutes to allow count rate to rise.DODD[38.3]NOTIFY Rx Engineering
to perform ICRR calculations
in accordance
with 0-RT-NUC-000-003.0.
[C.11]0[38.4]DETERMINE new count doubling range US.ING Appendix C.[39]IF reactor is subcritical
with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical
with Rods Fully Withdrawn.
0
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 34 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)
[40]IF IGRR plot indicates criticality
will fall outside+/-1000 pcm EGG termination
band, THEN[40.1]NOTIFY SM*andDuty Plant Manager.[40.2]EVALUATE if EGG should be recalculated
prior to continuing
startup.[40.3]IF startup mustbe aborted, THEN PERFORM Appendix 0, Acti*ons if Reactor Startup Must Be Aborted.0[41]IF IGRR plot trend indicates acceptable
EGG, THEN INITIATE rod withdrawal
USING 0-SO-85-1 to fifth doubling range (App.G)or criticality.
NOTE Steps 5.2[42]throu.gh 5.2[44]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.
[42]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds fifth doubling range determined
in Appendix G OR*Bank D rods reach fully withdrawn position OR D*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[43]IF reactor is critical, THEN GO TO Step 5.2[59](N/A Steps 5.2[44]through 5.2[58]).DDDD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 35 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
[44]IF ALL of the following conditions
are met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank D rods are below fully withdrawn position*Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
USING 0-SO-85-1 to fifth*doubling range or criticality (whichever
comes first).[45]IF source range*count rate has reached or exceeded fifth doubling range, THEN PERFORM the following:
[45.1]ENSURE rod motion STOPPED.[45.2]WAIT approximately
2-3 minutes to allow count rate to rise.Date----DODO[45.3]NOTIFY Rx Engineering
to perform ICRR calculations
in accordance
with O-RT-NUC-000-003.0.
[C.11]0[45.4]DETERMINE new count doubling range USING Appendix C.[46]IF reactor is subcritical
with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical
with Rods Fully Withdrawn.
o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 36 of 85 STARTUP No.Unit Date--"-'_5.2 Reactor Startup with Low Power Physics Testing (continued)
[47]IF ICRR plot indicates criticality
will fall outside+/-1000 pcm ECG termination
band, THEN[47.1]NOTIFY SM and Duty Plant Manager.[47.2]EVALUATE if EGC should be recalculated
prior to continuing
startup.[47.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.D[48]IF ICRR plot trend indicates acceptable
ECC, THEN INITIATE rod withdrawal
USING 0-SO-85-1 to sixth doubling range (App.G)or criticality.
NOTE*Steps 5.2[49]through 5.2[51]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.
[49]WHEN any ofthefollowing
conditions
are met:*Source range count rate reaches or exceeds sixth doubling range determined
in Appendix C OR*Bank 0 rods reach fully withdrawn position OR D*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[50]IF reactor is critical, THEN GO TO Step 5.2[59](N/A Steps 5.2[51]through
5.2[58]).DDDD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 37 of 85 5'.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
[51]IF ALL of the following conditions
are met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank D rods are below fully withdrawn position*Unit Supervisor
concurrence
is obtaine*d to resume, THEN RESUME rod withdrawal
USING 0-SO-85-1 to sixth doubling range or criticality (whichever
comes first).[52]IF source range count rate has reached or exceeded sixth doubling range, THEN PERFORM the following:
[52.1]ENSURE rod motion STOPPED.[52.2]WAIT approximately
2-3 minutes to allow count rate to rise.Date----DODD[52.3]NOTIFY RxEngineeringto
perform ICRR calculations
in , accordance
with 0-RT-NUC-000-003.0.
[C.11]D[52.4]DETERMINE new count doubling range USING Appendix C.[53]IF reactor is subcritical
with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical
with Rods Fully Withdrawn.
D
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 38 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
[54]IF IGRRplot indicates criticality
will fall outside+/-1000 pcm EGG termination
band, THEN[54.1]NOTIFY SM and Duty Plant Manager.[54.2]EVALUATE if ECG should be recalculated
prior to continuing
startup.Date------[54.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[55]IF IGRR plottrend indicates acceptable
EGG, THEN INITIATE rod withdrawal
to seventh doubling range (App.G)or criticality.
NOTE Steps 5.2[56]through 5.2[58]may be repeated as*necessary
if rod motion is stopped prior to reaching doubling range or criticality.
[56]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds seventh doubling range determined
in Appendix G OR*Bank D rods reach fully withdrawn position OR o*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[57]IF reactor is critical, THEN GO TOStep5.2[59](N/A Step 5.2[58]).DODD
SQN UNIT STARTUp*FROM HOT STANDBY O-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 39 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)
[58]IF ALL of the following conditions
are met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank 0"rods are below fully withdrawn position Date----*Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
USING 0-SO-85-1 to seventh doubling range or criticality (whichever
comes first).0000[59]IF any of the following conditions
exist:*critical conditions
cannot be achieved within the+/-1 OOOpcm allowable limits OR*critical conditions
cannot be achieved above rod insertion limit OR*reactor startup must be aborted for other reasons, THEN PERFORM the following to abort rea.ctof startup:[C.11][59.1]STOP rod withdrawal.
[59.2]INITIATE insertion of control banks.[59.3.]PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted.[59.4]DO NOT CONTINUE this section.o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028*Page 40 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power PhysicsTesting(continued)
[60]IF reactor is subcritical
with Bank D rods at fully withdrawn position, THEN PERFORM Ap.pendix E, Actions if Reactor is Subcritical
with Rods Fully Withdrawn.
D[61]IF reactor is critical with SUR less than 0.3 DPM AND intermediate
range NIS is less than P-6 (1 X 10-4%), THEN PERFORM the following:
[61.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately
0.3 DPM.[61.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering
concurs withRCS dilution, THEN PERFORM RCS dilution (as recommended
by Rx Eng)to establish positive SUR of approx.0.3 DPM USING 0-SO-62-7.
SQN UNIT STARTUP FROM HOT STANDBY*0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 41 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)
I Start of Critical Step(s)NOTES 1)Blocking the SRM reactor trip with[HS-92-5001]
and[HS-92-50021
will disable the detector outputs and remove the audio count rate signal.2)Step 5.2[62]may be performed at time of criticalit¥, if required.Source range reactor trip must be BLOCKED before trip setpoints of 10 cps.[62]WHEN annunciator
XA-55-4A, window D-2 P-6 INTERMEDIATE
RANGE is LIT, THEN[C.2]PERMISSIVE
[62.1]RECORD both source range readings.N-31 CPS---N-32 CPS---Initials[62.2]RECORD both intermediate
range readings.N-35%RTP---N-36%RTP---Initials[62.3]VERIFY a minimum of one IRM channel greater than or equal to1X 10-4%RTP.[62.4]BL*OCK source range reactor trip by momentarily
placing[HS-92-5001]
and[HS-9.2-5002]
SRM TRIP RESET-BLOCK
P-6 handswitches
to BLOCK.D Initials Date Time
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 42 of 85 STARTUP No.Unit Date----5.2 Reactor Startup with Low Power Physics (continued)
[62.5]VERIFY annunciator
XA-55-4A, window C-1 SOURCE RANGE TRAINS A.&B TRIP BLOCK is LIT.D I End of Critical Step(s)[62.6]SELECT NR 45 to record one intermediate
range channel and one power range channel.[62.7]ADJ'UST NR 45 chart speed as desired.(N/A is no change needed.)[63]ENSUR*EPA announcement
made to notify plant personnel when the reactor is critical.NOTE D D When T-avg is less than 551°F and Tavg-Tref deviation alarm is lit, SR 4.1.1.4.b requires verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes.[64]IF Tavg-Tref deviation alarm[M-5A window C-6]is LIT AND T-avg is less than 551°F, THEN PERFORM 0-SI-SXX-068-127.0
to satisfy SR 4.1.1.4.b, Minimum Temperature
For Criticality.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 43 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)
[65]RAISE reactor power to approximately1X 10-3%:[65.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive S*UR of approximately
0.5 DPM(not to exceed 1 DPM).[65.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering
concurs with RCS dilution, THEN PERFORM RCS dilution (as recommended
by Rx Eng)to establish positive SUR ofapprox.0.5 DPM USING 0-SO-62-7.
[65.3]WHEN intermediate
rangeNls indicate approximately1X 10-3%, THEN PERFORM the following:
[65.3.1]STABILIZE reactor power using control rods.[65.3.2]RECORD critical data indicated below.Power Level: Rod Position: N-35%RTP--N-36__0/0 RTP RCS Boron concentration
Loop TAVG: Bank Step 1 Initials 2 Date 3 ppm 4 Time[66]MAINTAIN reactor power stable with control banks above*Iowinsertionlimit
USING rod movement or boration/dilution
to compensate
for Xenon.o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 44 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)
[67]COORD.INATE
with Reactor Engineering
to perform Physics Testing USING O-RT-NUC-OOO-003.0.
0 NOTE If MSIVs are CLOSED, the reactor should be shut down to allow warming steam lines.[68]IF startup is to be discontinued
OR reactor startup was perf'ormed
with MSIVs closed, THEN GO TO 0-GO-6, Power Reduction From 30%Reactor Power to Hot Standby.[69]IF start up is to continue with one or both MFPTs available, THEN[69.1]ENSURE Steps 5.1[13]through 5.1[15]have been completed for applicable
pump(s).[69.2]VERIFY other applicable
actions Section 5.2 completed or initiated.
[69.3]GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5%Reactor Power.[70]IF start up is to continue with NO MFPT available, THEN[70.1]MARK Steps 5.1[13]through 5.1[17]as"N/A".END OF TEXT
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICALRev.0028 Page 45 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing[1]VERIFY applicable
actions in Section 5.1 completed or initiated.
Date---NOTE Steps 5.3[3]through 5.3[8]may be performed out ofsequence.
[2]IF any MFPT trip buss is NOT energized, TH*EN[2.1]ENSURE requirements
of LCO 3.0.4 are satisfied.
[2.2]NOTIFY Unit 8RO that LCO 3.3.2.1 (3.3.2)action 20 will apply when Mode 2 is entered.[3]ENSURE Appendix*B, Mode 3 to Mode 2, 1 Review and Approval has been completed to ensure all restraints
to Mode 2, 1 entry have been resolved and approvals for mode change granted.[4]BLOCK Source Range High Flux At Shutdown alarm:[4.1]PLACE BOTH HI FLUX AT SHUTDOWN switches on M-13 to the BLOCK position.[4.2]VERIFY annunciator
XA-55-4B window C-1 , SOURCE RANGE HIGH SHUTDOWN FLUX ALARM is LIT.[C.2].
CLOCK 8M o[5]VERIFY greater than or equal to 0.5 cps on the highest reading SR instrument.
o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 46 of 85 5.3 STARTUP No.Unit_Reactor Startup without Physics Testing (continued)
NOTE Date---The following count rates may be used as a reference during the approach to criticality.
[6]RECORD SR count rates from two of the following:
[C.2](N/A instruments
not used)XI-92-5001A (N31)cps XI-92-5002A (N32)cps OR XI-92-5001
B XI-92-5002B (N31)(N32)___cps_______cps Time Date[7]IF conditions
exist which could cause Power RangeNIS indications
to be non-conservative, THEN ENSURE Power Range high flux trip setpoints reduced to 60%in accordance
with the following:
[C.3]*1,2-SI-ICC-092-N41.1
0*1,2-SI-ICC-092-N42.2
0*1,2-SI-ICC-092-N43.3
0*1,2-SI-ICC-092-N44.4
0 Instrument
Maintenance
Date Time
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 47 of 85.5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[8]VERIFY the estimated critical position calculated
in accordance
with O-SI-NUC-000-001.0, Estimated Critical Conditions.
Date----Estimated critical position: Assumed boron concentration:
steps on bank ppm Initials STA Time Time Date Date[9]VERIFY*Steps 5.3[1]through 5.3[8]completed.
[10]IF estimated critical boron concentration
does NOT approximately
equal actual boron concentration, THEN[10.1]DETERMINE the appropriate
boration/dilution
requirements
to achieve criticality
within acceptable
limits.D[10.2]DILUTE/BORATE
in accordance
with 0-80-62-7 to the estimated critical boron concentration.
[C.12]0[10.3]OPERATE pressurizer
heaters/spray
as necessary to equalize boron concentration (within 50 ppm)between reactor coolant loops and the pressurizer.
[C.12]D[to.4]WHEN sufficient
mixing has occurred, THEN OBTAIN a new boron sample.D[10.5]ENSURE actual boron concentration
is approximately
equal to the estimated critical boron concentration.
SQN UN*IT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 48 of 85 STARTUP No.----Unit---Date----5.3 Reactor Startup without Physics Testing (continued)
NOTE Termination
limits are associated
with+/-750 pcm tolerance band.These values are within minimum and maximum rod positions corresponding
to Tech Spec limit of+/-1000 pcm (Minimum and Maximum Allowable Limits).Termination
limits shall be used by Reactor Engineering
and Operations
to determine whether approach to criticality
should be terminated
and a new ECC calculated.
ECC must be terminated
if Minimum or Maximum Allowable Limits (corresponding
to Tech Spec limit of+/-1000 pcm)are approached.
[11]RECORD upper and lower rod position limits corresponding
to+/-750 pcm Termination
Band as determined
by 0-SI-NUC-000-001..0, Estimated Critical Conditions.
Upper termination
rod position Lower termination
rod position steps on bank steps on bank Initials Time Date[12]RECORD minimum and maximum rod positions corresponding
to+/-1000 pcm ALLOWABLE LIMITS (Tech Spec Limit)determined
by 0-SI-NUC-000-001.0, Estimated Critical Conditions.
[C.11]Minimum allowable rod position Maximum allowable rod position steps on*bank steps on bank Initials Time Date[13]VERIFY all shutdown rods are fully withdrawn in accordance
with 0-SI-OPS-000-004.0, Surveillance
Requirements
Performed on In'creased
Frequency with no Specific Frequency, within 15 minutes prior to withdrawing
control rods.Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 49 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
NOTE Date----SR 4.1.1.4.a requires verifying lowest T-avggreater
than_or equal to 541°F within 15 minutes prior to achieving criticality.
[14]IF O-SI-SXX-068-127.0
is NOT in progress, THEN INITIATE applicable
sections of O-SI-SXX-068-127.0
to satisfy SR 4.1.1.4.a., Minimum Temperature
For Criticality.
[15]NOTIFY onsite personnel of reactor startup over PIA system.D CAUTION Avoid operations
that-could
produce sudden changes of temperature
or unplanned boron concentration
changes during approach to criticality
or low power.NOTES 1)Nuclear instrumentation
shall be monitored very closely for indications
of unplanned reactivity
rate of change.[C.11]2)Activities
that can distract operators and supervisors
involved with reactor startup, such as shift turnover and surveillance
testing during approach to criticality, SHALL BE avoided.[C.12]3)ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for monitoring
NIS indications.
[16]MONITOR nuclear instruments
during approach to criticality:
[16.1]MONITOR source rang-e and intermediaterangeNIS to identify potential reactivity
anomalies.
[C.11][16.2]IF desired to placeNR-45
recorder in fast speed, THEN ADJUST chart speed to high.D
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 50 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
CAUTION Date---Do NOT exceed a steady startup rate of+1 DPM.NOTE The unit enters Mode 2 when the control banks are first withdrawn.
[17]INITIATE a reactor startup by performing
the following:
[17.1]RECORD*both source range readings for ICRR base counts.N-31 CPS---N-32 CPS---Initials[17.2]RECORD intermediate
range readings.N-35 0/0---N-36 0/0---Initials[17.3]CALCULATE initial source range count doubling value USING Appendix C.MODE 2[17.4]INITIATE withdrawal
of control banks in accordance
with 0-SO-85-1 to first stop point: CONTROL BANK A 128 STEPS[17.5]ENSURE Mode 2 entry'is logged (log entry may be performed out of sequence later).o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 51 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[18]WHEN control bank A is at128 steps, THEN PERFORM the following:
[18.1]STOP rod withdrawal.
[18.2]WAIT for approximately
two minutes.[18.3]N'OTIFY Rx Engineering
to perform ICRR calculation
in accordance
with 0-81-NUC-OOO-001.0.
[C.11]CAUTION Date---Lowest loop T-avg must be verified greater than or equal to 541°F using 0-SI-SXX-068-127.0within
15 minutes prior to achieving criticality.
NOTES1)Approximately
five to seven count doublings are expected to result in criticality.
However, criticality
should be anticipated
at.a*ny time.2)Proper bank overlap must be verified using 0-80-85-1 as each successive
rod bank is withdrawn.
[19]WHEN concurrence
obtained from Rx Engineering, THEN INITIATE rod withdrawal
to first count doubling (determined
in App.C)USING 0-80-85-1.
D
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 52 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
Date---NOTE Steps 5.3[20]and 5.3[21]may be repeated as necessary if rod motion is stopped prior to reaching doubling value.[20]WHEN any of the following conditions
are met:*Source range count rate is approximately
equal to first-doubling
value determined
in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-80-85-1)
OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[21]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
to first count doubling USING
[22]IF source range count rate has reached or exceeded first doubling, THEN PERFORM the following:
[22.1]ENSURE rod motion STOPPED.[22.2]WAIT approximately
2-3 minutes to allow count rate to rise.DODD DODD[22.3]NOTI*FYRx Engineering
to perform ICRR calculations
in accordance
with O-SI-NUC-000-001.0.
[C.11]D[22.4]DETERMINE new count doubling range USING Appendix C.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 53 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continu.ed)
[23]IF ICRR plot indicates criticality
will fall outside+/-750 pcm ECC termination
band, THEN[23.1]NOTIFY SM and Duty Plant Manager.[23.2]EVALUATE if ECC should be recalculated
prior to continuing
startup.Date----[23.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.D[24]WHEN concurrence
obtained from Rx Engineering, THEN INITIATE rod withdrawal
to second doubling range (determined
in App.C)USING 0-80-85-1.
NOTE Steps 5.3[25]and 5.3[26]may be repeated as necessary if rod motion is stopped prior to reaching doubling range.[25]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds second doubling range determined
in Appendix C OR*C'ontrol bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)
OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.o DODD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 54 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[26]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
to second doubling range USING 0-SO-85-1.
[27]IF source range count rate has reached or exceeded second doubling range, THE*N PERFORM the following:
[27.1]ENSURE rod motion STOPPED.[27.2]WAIT approximately
2-3 mi'nutes to allow count rate to rise.Date---0000[27.3]NOTIFY Rx Engineering
to perform ICRR calculations
in accordance
with 0-SI-NUC-000-001.0.
[C.11]0[27.4]DETERMINE new count doubling range USING Appendix C.[28]IF ICRR plot indicates criticality
will fall outside+/-750 pcm ECC termination
band, THEN[28.1]NOTIFYSM and Duty Plant Manager.[28.2]EVALUATE if ECC should be recalculated
prior to continuing
startup.[28.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[29]IF ICRR plot trend indicates acceptable
ECC, THEN IN'ITIATE rod withdrawal
to third doubling range (determined
in App.C)USINGO-SO-85-1.
o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 55 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
Date----NOTE Steps 5.3[30]and 5.3[31]may be repeated as necessary if rod motion is stopped prior to reaching doubling range.[30]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds third doubling range determined
in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)
OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[31]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
to third doubling range USING 0-SO-85-1.
[32]IF source range count rate has reached or exceeded third doubling range, THEN PERFORM the following:
[32.1]ENSURE rod motion STOPPED.[32.2]WAIT approximately
2-3 minutes to allow count rate to rise.DODD DODD[32.3]NOTIFY Rx Engineering
to perform leRR calculations
in accordance
with
[C.11]0[32.4]DETERMINE new count doubling range USING Appendix C.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 56 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[33]IF ICRR plot indicates criticality
will fall outside+/-750 pcm ECC termination
band, THEN
NOTIFY SM and Duty Plant Manager.[33.2]EVALUATE if ECC should be recalculated
prior to continuing
startup.Date---[33.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[34]IF ICRRplot trend indicates acceptable
ECC, THEN INITIATE rod withdrawal-USING
0-80-85-1 to fourth doubling range (App.C)or criticality.
NOTE Steps 5.3[35]through 5.3[37]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.
[35]WHEN any of the foHowing conditions
are met:*Source range count rate reaches or exceeds fourth doubling range determined
in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-80-85-1)
OR*Bank D rods reach fully withdrawn position OR o*Operators or Rx Engineer determine that rod motion shoul-d be stopped THEN STOP outward rod motion.DOOD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 57 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[36]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Steps 5.3[37]through 5.3[58]).[37]I*F ALL of the following conditions
are met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank D rods are below fully withdrawn position*Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
USING 0-SO-85-1 to fourth doubling range or criticality (whichever
comes first).[38]IF source range count rate has reached or exceeded fourth doubling range, THEN PERFORM the following:
[38.1]ENSURE rod motion STOPPED.[38.2].WAIT approximately
2-3 minutes to allow count rate to rise.*Date----DODD[38.3]NOTIFY Rx Engineering
to perform leRR calculations
in accordance
with O-SI-NUC-OOO-001.0.
[C.11]D[38.4]DETERMINE new count doubling range USING Appendix C.[39]IF reactor is subcritical
with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical
with Rods Fully Withdrawn.
D
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 58 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[40]IF ICRR plot indicates criticality
will fall outside+/-750 pcm ECC terminati*on
band, THEN[40.1]NOTIFY SMand Duty Plant Manager.[40.2]EVALUATE ifECC should be recalculated
prior to continuing
startup.Date---[40.3]IF startup must be aborted, THEN PERFO*RM Appendix 0, Actions if Reactor Startup Must Be Aborted.D[41]IF ICRR plot trend indicates acceptable
ECC, THEN INITIATE rod withdrawal
U5INGO-SO-85-1
to fifth doubling range (App.C)or criticality.
NOTE Steps 5.3[42]through 5.3[44]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.
[42]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds fifth doubling range determined
in Appendix C OR*Bank D rods reach fully withdrawn position OR D*Operators orRx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[43]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Steps 5.3[44]through 5.3[58]).DDDD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 59 of 85 5.3 STARTUP No.Unit------Reactor Startup without Physics Testing (continued)
[44]IF ALL of the following conditions
are met:*rod motion was stopped'prior to reaching doubling range or criticality
*Bank.D rods are below fully withdrawn position*Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
USING 0-SO-85-1 to fifth doubling range or criticality (whichever
comes first).[45]IF source range count rate has reached or exceeded fifth doubling range, THEN PERFORM the following:
[45.1]ENSURE rod motion STOPPED.[45.2]WAIT approximately
2-3 minutes to allow count rate to rise.Date---DOOO[45.3]NOTIFY Rx Engineering
to perform ICRR calculations
in accordance
with O-SI-NUC-OOO-001.0.
[C.11]D[45.4]DETERMINE new Gount doubling range USING Appendix C.[46]IF reactor is subcritical
with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical
with Rods Fully Withdra*wn.
0
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 60 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[47]IF IGRR plot indicates criticality
will fall outside+/-750 pcm EGG termination
band, THEN[47.1]NOTIFY SM and Duty Plant Manager.[47.2]EVALUATE if EGO should be recalculated
prior to continuing
startup.Date---[47.3]IF startup must be aborted, THEN PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted.0[48]IF IGRR plot trend indicates acceptable
EGG, THEN INITIATE rod withdrawal
USING 0-SO-85-1 to sixth doubling range (App.G)or criticality.
NOTE Steps 5.3[49]through 5.3[51]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.
[49]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds sixth doubling range determined
in Appendix C OR*Bank 0 rods reach fully withdrawn position OR o*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[50]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Steps 5.3[51]through 5.3[58]).DODD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 61 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[51]IF ALL of the following conditions
are met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank D rods are below fully withdrawn position*Unit Supervisor
concurrence
is obtained to resume, THEN RESUME rod withdrawal
USING 0-80-85-1 to sixth doubling range or criticality (whichever
comes first).[52]IF source ran'ge count rate has reached or exceeded sixth doubling range, THEN PERFORM the following:
[52.1]ENSURE rod motion STOPPED.[52.2]WAIT approximately
2-3 minutes to allow count rate to rise.Date----DDDD[52.3]NOTIFY Rx Engineering
to perform ICRR calculations
in accordance
with 0-SI-NUC-000-001.0.
[C.11]0[52.4]DETERMINE new count doubling range USING Appendix C.[53]IF reactor is subcriUcal
with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if"Reactor is Subcritical
with Rods Fully Withdrawn.
D
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 62 of 85 5.3 STARTUP No.UnitReactor Startup without Physics Testing (continued)
[54]IF ICRR plot indicates criticality
will fall outside+/-750 pcm ECC termination
band, THEN[54.1]NOTIFY SM and Duty Plant Manager.[54.2]EVALUATE if ECC should be recalculated
prior to continuing
startup.Date---[54.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.O'[55]IF ICRR plot trend*indicates
acceptable
ECC, THEN INITIATE rod withdrawal
USINGO-SO-85-1
to seventh doubling range (App.C)or criticality.
NOTE Steps 5.3[56]through 5.3[58]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.
[56]WHEN any of the following conditions
are met:*Source range count rate reaches or exceeds seventh doubling range determined
in Appendix C OR*Bank D rods reach fully withdrawn position OR D*Operators or RxEng.ineer
determine that rod motion should be stopped THEN STOP outward rod motion.[57]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Step 5.3[58]).DODD
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR'CRITICAL Rev.0028 Page 63 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
[58]IF ALL of the followingconditionsare
met:*rod motion was stopped prior to reaching doubling range or criticality
*Bank D rods are below fully withdrawn position Date----*Unit Supervisor
concurrence
is obtained to resume, THEN RES*UME rod withdrawal
USING 0-SO-85-1 to seventh doubling range or criticality (whichever
comes first).0000[59]IF any of the following conditions
exist:*critical co.nditions
cannot be achieved within the+/-750 pcm termination
band OR*critical conditions
cannot be achieved within the+/-1 000 pcm allowable limits OR*critical conditions
cannot be achieved above rod insertion limit OR*reactor startup must be aborted for other reasons, THEN PERFORM the following to abort reactor startup:[C.11][59.1]STOP rod withdrawal.
[59.2]INITIATE insertion of control banks.[59.3]PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.[59.4]DO NOT CONTINUE this section.o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 64 of 85 STARTUP No.
Unit---Date---5.3 Reactor Startup without Physics Testing (continued)
[60]IF reactor is subcritical
with BankO rods at fully
THEN PERFORM Appendix E, Actions if Reactor is Subcritical
with Rods Fully Withdrawn.
0[61]IF reactor is critical with SUR less than 0.3 DPM AND intermediate
range NIS is less than (1 X 10-4%), THEN PERFORM the following:
[61.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately
0.3 DPM.[61.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering
concurs with RCSdilution, THEN PERFORM RCS dilution (as recommended
by Rx Eng)to establish positive SUR of approx.0.3 OPM USING 0-80-62-7.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 65 of 85 5.3 STARTUP No.Unit---Reactor*Startup
without Physics Testing (continued)
I Start of Critical Step(s)Date---NOTES 3)Blocking the SRM reactor trip with[HS-92-50011
and[HS-92-50021
will disable the detector outputs and remove the audio count rate signal.4)Step 5.3[62]may be performed at time of criticality, if required.Source range reactor trip must be BLOCKED before trip setpoint of 10 5 cps.[62]WHEN annunciator
XA-55-4A, window 0-2 P-6 INTERMEDIATE
RANGE PERMISSIVE
is LIT, THEN[C.2][62.1]RECORD both source range readings.N-31 CPS---N-32 CPS---Initials[62.2]RECORD both intermediate
range readings.N-35%RTP N-36%RTP Initials[62.3]VERIFY a minimum of one IRMchannel
greater than or equal to1X 10-4%RTP.0[62.4]BLOCK source range reactor trip by momentarily
placing[HS-92-50011
and
SRM TRIP RESE*T-BLOCK P-6 handswitches
to BLOCK.Initials Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO-REACTOR CRITICAL Rev.0028 Page 66 of 85 Date---5.3 SOURCE RANGE TRAINS A&B TRIP BLOCK is LIT.o I End of Critical Step(s)[62.6]SELECT NR 45 to record one intermediate
range channel and one power ran-ge channel.[62.7]ADJUST NR45 chart speed as desired.(N/A if no change needed).[63]ENSURE PA announcement
made to notify plant personnel when the reactor is critical.NOTE D D o When T-avg is less than 551°F and Tavg-Tref deviation alarm is lit, SR 4.1.1.4.b requires verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes.[64]IF Tavg-Tref deviation alarm[M-5A window C-6]is LIT AND T-avg is less than 551°F, THEN PERFORM O-SI-SXX-068-127.0
to satisfy SR 4.1.1.4.b, Minimum Temperature
For Criticality.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 67 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
,[65]RAISE reactor power to approximately
1X 10-3%:[65.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately
0.5 DPM (not to exceed 1 DPM).[65.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering
concurs with RCS dilution, THEN PERFORM RCS dilution (as recommended
by Rx Eng)to establish positive SUR of approx.0.5 DPM USING 0-SO-62-7.
[65.3]WHEN intermediate
range NIS indicate approximately1X 10-3%, THEN PERFORM the following:
[65.3.1]STABILIZE reactor power using control rods.[65.3.2]RECORD critical data indicated below.Date----Power Level: N-35%RTP---N-36%RTP---Rod Position: RCS Boron concentration
Loop TAVG: Bank 1 Step 2 3 Initials ppm 4 Time Date[66]VERIFY control rods above rod ins*ertion
limit USING 1,2-SI-OPS-OOO-002.0, Shift Log.[67]MAINTAIN reactor power stable with control banks above low insertion limit USING rod movement or boration/dilution
to compensate
for Xenon.o o
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 68 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)
Date---NOTE If MSIVs are CLOSED, the reactor should be shut down to allow warming steam lines.[68]IF startup is to be discontinued
OR reactor startup was performed with MSIVs closed, THEN GO TO 0-GO-6, Power Reduction From 30%Reactor Power to Hot Standby.[69]IF start up is to continue with one or bothMFPTs available, THEN[69.1]ENSURE Steps 5.1[13]through 5.1[15]have been completed for applicable
pump(s).[69.2]VERIFY other applicable
actions in Section 5.3 completed or initiated.
[69.3]GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5%Reactor Power.[70]IF start up is to continue with NO MFPT available, THEN[70.1]MARK Steps 5.1[13]through 5.1[17]as"N/A".[70.2]VERIFY other applicable
actions in Section 5.3 completed or initiated.
[70.3]GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5%Reactor Power.END OF TEXT
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 69 of 85 6.0 RECORDS Completed copies shall be transmitted
to the Operations
Superintendent's
Secretary.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 70 of8S Appendix A (Page 1 of 1)DELETED 1.0 DELETED
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 71 of 85 1.0 Appendix B (Page 1 of 8)MODE 3 TO MODE 2,1 REVIEW AND APPROVAL STARTUP No.Unit------'--MODE 3 TO 2,1 REVIEW AND APPROVAL
NOTE Steps in this Appendix may be performed out of sequence, except for those steps that pertain to the Operations
Superintendent
Hold Point.[1]PRIOR to entering Mode 2, 1, an SRO shall review the following:
NOTE Mode 3 to Mode 2, 1 Checklist and Reactor Trip Breaker Checklist are to be attached to this instruction.
tJ{;Vo Time A.Mode 3 to Mode 2,1 Checklists
from the responsible
sections and DETERMINE thatthe required surveillance
testing for Mode 2 entry has been co pleted
Da e Of&00YO Time.jO].C2?'1 0 Time c.Active clearances
for mode ch nge restraints.
I 1 B.Reactor Trip Breaker Closure C'ecklists from the responsible
sections and DETE*RMINE
that required surveillance
testing for mode change has been completed.
l D.TACF Books for outstanding
alternations
on systems prior to declaring a T.S.system or comp: ent 0 e ble.[C.10]!01 Time at
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 72 of 85
1.0 Appendix B (Page 2 of 8)STARTUP No.Unit J----1('----
MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)
E.O-TI-EXX-OOO-001.0, Electrical
Jumper Control Log to determine if any potential T.S.restriction
exists which would prevent a mode chang*f1jJ i2ill Time tJ/Iv 1/j,.;F.Active Procedures
Book to determine equipment status that may be abnormal.nri G Unql()Time (j1VJ Time G.OPDP-4, Annunciator
Disablement
Log for alarms affecting operability
of equipment required for mode change.H.O-PI-OPS-301-001.0Plant
Computer Point Disablement
Log for alarms affecting operability
of equipment required for mode change.I.Board walkdown is completed to verify proper equipment alignment.(Refer to appropriate
CRO and GATC Pis for guidance)[C.10]OJ..61/v;<,./uf*(//ylJ
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 73 of 85 1.0 Appendix B (Page 3 of 8)STARTUP No.Unit+MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)
NOTE Tech Spec and TRM LCO 3.0.4 govern entering Mode 2 if,any LCO requirement
applicable
in Mode*2is not met.Therefore, mode change is not allowed while in a Tech Spec or TRMaction UNLESS the exceptions
and/or allowances
stated in LCO 3.0.4 can be applied.J.RE*VIEW all Tech Spec and TRM Actions which have been entered on the affected unit and common equipment to verify that mode change is acceptable.
SRO SRO Time Time Date Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 74 of 85 2.0 Appen.dix B (Page 4 of 8)STARTUP No.UnitDEPARTMENT
MANAGERS REVIEW 2.1 Periodic Test Coordinator:
.Instrument
Maintenance:
&deg;tXr/o f ate OZIO Time PiOdlC Test Coordinator
ENSURE that all surveillance
requirements
for m de 2 entry are updated and included Withiit e c!han checklist.
.i./&/0 7t i dic Te oordinator
Time ENSURE that all surveilianceV:eqUirements
for Reactor Trip Breaker Closure Checklist are updated and included within the checklist.
[e.9][2][1]2.2[1]ENSURE Wide Range SG Level Recorders[LR-3-43A]
and[LR-3-98A]areOPERABLE
and SET to a range requested by the operator.(Recommended
range between 80 and 90%of scale).[C.6]
4JfIOJ Time'at 2.3 Fire Ops Section:[1]Oil%
Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 75 of 85 Appendix B (Page 5 of 8)I Unit----'--STARTUP No.____2.4 Systems Engineering
Section:[1]REVIEW of mode change checklist is complete and all surveillance
requirements
have met their acceptance
criteria for Mode 2 entry.Shift Manager[2]REVIEW of Reactor Trip Breaker Closure Checklist is complete, all surveillance
requirements
have met their acceptance
criteria, and all open items that affect modechangehave
been closed.Time Date Shift Manager Time Date NOTE The evaluation
made by the Systems Engineer in the next step will prevent thermal shock to the PZR spray nozzle.[3]ENSURE PZR spray line bypass valves are throttled to maintain acceptable
spray line temperature*
in accordance
with 0-SO-68-3.
:f&#xa3;JYWL&1f;t;System En'gineering
Time orfr;fal ate[4]IF startup is following a refueling outage, THEN ENSURE Present Cycle Core Operating Limit Report are inserted in the unit's Technical specU/oon
C.7]r If!f f f...ilsing
or designee OGO(
1 0)Time ate f'
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 76 of 85 2.5 STARTUP No.----Maintenance
Section: Appendix B (Page 6of8)Unit-l-Date fJ tjV;;/Ol[1]REVIEW of mode change checklist is complete and all surveillance
requirements
have met their acceptance
criteria for Mode 2 entry.Shift Manager[2]REVIEW of Reactor Trip Breaker Closure Checklist is complete, aH surveillance
requirements
have met their acceptance
criteria, and all open items that affect mod"e change have been closed.Shift Manager 2.6 Chemistry Section: NOTE Time Time Date Date The following step does not require a new analysis to be performed for this startup.Routine analysis is sufficient
unless there is reason to suspect chemistry has been changed.[1]ENSURE reactor coolant chemistry within limits of Technical Requirements
Manual 3.4.7 as determined
by the Chemical Shift Supervisor.
4 obJO*J
oj Time
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 77 of 85 Appendix B (Page 7 of 8)3.0 STARTUP No.Unit---SHIFT MANAGER (SM)HOLD POINT[1]ENSURE Tech Spec and non-Tech Spec work related activities
are completed or will not prohibit entry or impact continued operation in Mode 2.Date8M Time Date[2]ENSURE no open DCN/ECNsthat
would prohibit a mode change.(SM concurrence
with the Modifications
Manager or designee).
SM Time Date[3]REVIEW all open work activities
relative to the unit for the purpose of identifying
maintenance
activities
that could affect system operability
prior to mode change SM[4]IF any potential Tech Spec.mode constraint
exists, THEN OBTAIN Operations
Superintendent
resolution
prior to proceeding
with the mode change SM Time Time Date Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 78 of 85 Appendix B (Page 8 of 8)3.0 STARTUP No.Unit---SHIFT MANAGER (8M)HOLD POINT (continued)
[5]IF the startup follows a reactor trip or an emergency shutdown, THEN Date---A.ENSURE cause of the trip/shutdown
has been determined
and will not impact Mode 2 entry.SM B.ENSURE Reactor trip report is complete.Time Date (0-TI-QXX-000-001.0, Event Critique, Post Trip Report, Equipment Root Cause and Outage Milestone PER Evaluation)
SM Time Date c.ENSURE 0-GO-12, Realignment
of Secondary Equipment Following Reactor TriplTurbine
Trip/Emergency
shutdown, is complete.SM Time Date 4.0 OPERATIONS
SUPERINTENDENT
HOLD POINT Operations
Superintendent
or his designee concurs and grants approval to proceed to Mode 2, 1.Operations
Superintendent
Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 79 of 85 Appendix C (Page 1 of 1)DETERMINING
SOURCE RANGE COUNT RATE DOUBLING 1.0 CALCULATING
DOUBLING RANGE NOTES1)Source range reading shal.l be allowed to stabilize for approximately
3 minutes after each reactivity
change prior to determining
new stable count rate.2)The highest reading channel should be used when determining
stable count rate.3)Doubling range is used to determine when rod motion should be stopped during approach to criticality.
Criticality
is expected in about 5 to 7 count rate doublings.
4)This appendix may be performed and IV'd by operators, ST A, or Rx Engineers.
STABLE COUNT RATE DOUBLING RANGE INITIALS COUNT RATE (CR)CR X 1.75=CR X 2.0=1st IV (Lower value not used for first doubling)End of Section
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 80 of 85 Appendix D (Page 1 of 1)ACTIONS IF REACTOR STARTUP MUST BE ABORTED 1.0 STARTUP No.OPERATOR ACTIONS Unit---CAUTION Date---If reactor trip is required, E-O should be performed instead of this appendix.[1]ENSURE all control bank rods FULLY INSERTED in accordance
with 0-SO-85-1.
[2]LOG Mode 3 entry in narrative log.[3]VERIFY adequate shutdown margin in accordance
with 0-SI-NUC-000-038.0.
[4][5]Initials DETERMINE and CORRECT cause of the discrepancy.
WHEN reactor startup is to resume, THEN PERFORM the following:
[5.1]RECALCULATE-estimated
critical conditions
in accordance
with 0-RT-NUC-000-003.0(Startup
after refueling)
or 0-SI-NUC-000-001.0 (Startup after non-refueling
outage).Time Date o[5.2]DILUTE/BORATE
in accordance
withO-SO-62-7
to the estimated critical boron concentration.
[C.12][5.3]EQUALIZE boron concentration (within 50 ppm)between reactor coolant loops and pressurizer
by operating pzr heaters and spray.[C.12][5.4]R-E-INITIATE
0-GO-2.End of Document
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 81 of 85 Appendix E (Page 1 of 2)ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY
1.0 OPERATOR ACTIONS NOTE Allowable upper limit for critical position may be above the fully withdrawn position on Bank D.If Reactor Engineering
determinesthatcore response is within acceptable
limits, this appendix allows RCS dilution to assist in achieving criticality.
[1]CONSULT Reactor Engineering
to determine if core response is within acceptable
limits.D[2]IF projected critical rod position exceeds+1000 pcm limit OR startup will be aborted due to failing to achieve criticality, THEN[2.1][2.2]PERFORM AppendixD, Actions if Reactor Startup Must Be Aborted..DO NOT CONTINUE this appendix.D D[3]ENSURE control bank D inserted to less than or equal to estimated critical position determined
in O-RT-NUC-000-003.0 (Startup after refueling)
or O-SI-NUC-000-001.0 (Startup after non-refueling
outage).[4]DETERMINE dilution volume to increase core reactivity
by 100 pcm OR as recommended
by Rx Engineering.
gallons-----Rx Engineer IV
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 82 of 85 Appendix E (Page 2 of 2)1.0 STARTUP No.Unit------OPERATOR ACTIONS (continued)
CAUTION Date---NISindications
should be carefully monitored during and following dilution.[5][6]PERFORM specified dHution USING 0-80-62-7.
WHEN at least30 minutes has elapsed for ReS mixing AND RxEngineer
concurs with resuming startup, THEN RETURN to appropriate
step (based on number of doublings)
in Sect.5.2 (Startup after refueling)
or Section 5.3 (Startup after non-refueling
outage).End of Document D D
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 83 of 85 Source Notes (Page 1 of 3)Requirements
Statement Verify MFWP trip bus energized before entry into Mode 2.Revise GOI-2 to require verification
of intermediate
range (IR)status at approximately
20 and 25 percent, verify source range (SR)status and channel check at lower power, monitor core delta Ts at low-power levels and during power escalation
and compare with N IS response, and verify that the IR rod stop and trip bistables come in at the appropriate
power level during power ascension.
Following refueling operations
relocation
of NIS or modifications
affecting the NIS response, provide adequate reductions
of trip setpoint and limitations
of reactor power until accuracy of the NIS is verified.Also, provide alternate indications
of power independent
of calorimetric
calculations
during power ascensions.
Decommitted
3/12/99 Assurance that TSC computer is reset prior to startup;defines"reset" and"updating".(Modified C.5 permitting
relaxing requirement.)
Provisions
to ensure that enhanced steam generator level recorders are operable in the main control room prior to entering mode 2.Source Document LER 328/88-014
NCO 890118002 LER 328/89006 S53 890531 844 JRBto NRC SOER-90-003
NCO 900107009 NER 1187001 LER 327/90011R1
Verbal commitment
to NRC at SNP Meeting 10/04/90 NCO 890097004 L44 890505 805 Implementing
Statement C.1 C.2 C.3 C.4 C.S C.6
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 84 of 85 Source Notes (Page 2 of 3)Requirements
Statement Based upon the requirements
of the May 6, 1991 PORC meeting this verification
has been added to implement the referenced
Technical Specification
change for the Core Operating Limits Report.Consult Reactor Engineerin*g
for guidance during evolutions
of unusual power maneuvers at end of core life.Provide reactor trip breaker closure checklists
to ensure all surveillance
requirements
for reactor trip breaker closure are satisfied.
Revise
to include a step signoff with the T ACF review, hold order review etc.section of GOI, for the Duty SOS to ensure a board walkdown to verify proper alignment is performed by a designated
*SRO prior to mode change.Op*erations
startup procedures
should:1)Stress conservative
actions and compliance
with written procedures
when repositioning
control rods, 2)Guidance on actions whe.n criticality
will be achieved outside the ECC tolerance band, 3)Avoid activities
which distract the operators, 4)Directions
to use pertinent instrumentation
to monitor approach to criticality, 5)Periodic pauses during rod withdrawal.
Source Document PORC Minutes#50880 5/06/91T/891-08
NER 89 0794 OER 89 3497U1 C5 Outage Critique item 118-92-045
80ER 88-02 NER 88047400 Implementing
Statement C.7 C.8 C.g C.10 C.11
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 2 of 77 TABLE OF CONTENTS Page 1 of 2 Section Title Page 1.0 INTRODUCTION
"......................................................................
4 1.1 Purpose......
4 1.2 Scope................................................................................................................
4 2.0 REFERENCES..................................................................................................
4 2.1 Performance
References..................................................................................
4 2.2 Developmental
References...............................................................................
4 3.0 PRECAUTIONS
AND LIMITATIONS................................................................
6 4.0 PREREQUISITE
ACTIONS..9 5.0 STARTUP/STANDBY
READINESS 10 5.1 Placing MG Set(s)in Standby Readiness............................
10 5.1.1 Placing MG Set A In Service With MG Set B NOT Operating 12 5.1.2 Placing MG Set B In Service With MG Set A NOT Operating 15 5.2 Reset/Close
Reactor Trip Breakers..................................................................
18 6.0 NORMAL OPERATION 21 6.1 Placing MG Set A In Service With MG Set B Operating.........
21 6.2 Placing MG Set B In Service With MG Set A Operating 30 6.3 Manual Operation of Rod Control System Below 15 Percent Power................
39 6.4 Transferring
from Manual to Auto Rod Control.................................................
52 6.5 Transferring
from Auto to Manual Rod Control.................................................
53 7.0 SHUTDOWN.....................................................................................................
54 7.1 Removing the MG Set A From Service 54 7.2 Removing the MG Set B From Service 55
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 3 of 77 TABLE OF CONTENTS Page 2 of 2 Section Title Page 8.0 8.1 8.2 8.3
8.4 8.5 8.6 9.0 INFREQUENT
OPERATION.Alternate Method of Paralleling
MG Set A.Alternate Method of Paralleling
MG Set B.Resetting Step Counters After Withdrawing
Rods Above 231 Steps.Resetting Step Counters After Inserting Rods Below 0 Steps.Placing MG Set A In Service for Maintenance
.Placing MG Set B In Service for Maintenance
.RECORDS.56 56 58 60 61 62 69 76 SOURCE NOTES 77 ATTACHMENTS
ATTACHMENT
1: ATTACHMENT
2: CONTROL ROD DRIVE SYSTEM POWER CHECKLIST 1-85-1.01 CONTROL ROD DRIVE SYSTEM POWER CHECKLIST 2-85-1.01
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 4 of 77 1.0 INTRODUCTION
1.1 Purpose This instruction
provides the steps necessary for the operation of the Control Rod Drive System.1.2 Scope This instruction
provides detailed steps for the following operations:
Placing Control Rod Drive MG Sets in Service Removing Control Rod Drive MG Sets from Service Parallel Operation of Control Rod Drive MG Sets Manual Operation of the Control Rod Drive System Transferring
Rod Control from Manual to Auto Transferring
Rod Control from Auto to Manual 2.0 REFERENCES
2.1 Performance
References
A.Procedures
1.0-SI-NUC-000-038.0, Shutdown Margin 2.1 ,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts B.Tech Specs 1.3.4.1.2 C.Westinghouse
Tech.Bulletin NSD-TB-92-05RO
2.2 Developmental
References
A.Tech Specs 1.3.1.3.1 2.3.1.3.2 3.3.1.3.4 4.3.1.3.5 5.3.1.3.6
SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 5 of 77 2.0 REFERENCES (Continued)
B.Technical Requirements
Manual 1.TR 3.1.3.3 C.F8AR 1.7.7.1.2.1 D.TVA Drawings 1.45N699-1 2.45N777-3 3.45N703-1, 2, 3,4 4.45N1646-4 5.45N2646-4 6.45N1624-1, 2, 3,4, 5, 8 7.45N2624-1, 2, 3,4, 5, 8 8.617F619
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 6 of 77 3.0 PRECAUTIONS
AND LIMITATIONS
A.Rod thermal lock-up is NOT a concern when the reactor trip breakers are OPEN.If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50&deg;F is planned, the shutdown and control banks should be withdrawn at least 5 steps each.This will limit the possibility
of"thermalup" of the rods.This does not apply if performing
sections 8.5 or 8.6.B.If both MG sets are to be shutdown, the control rods and shutdown rods shall be inserted in the core and the reactor trip breakers OPEN prior to shutting down the MG sets.C.Reactor Trip Breakers shall NOT be closed while in Mode 3 unless in compliance
with LCO 3.4.1.2.D.Failure to perform 1 ,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts could result in the prevention
of AUTO SI if required.E.Under normal conditions, the control rod banks must be withdrawn and inserted in the prescribed
sequence.For withdrawal
the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, and Control Bank D.The insertion sequence is the reverse of the withdrawal
sequence.F.For manual bank sequencing, the prescribed
withdrawal
and insertion sequence should be followed.Rod motion of the correct bank should be monitored by observing the group step counters and the rod position indicators.
G.During Control Rod withdrawal, the Control Banks should be monitored for bank overlap.H.The control banks must be maintained
above their respective
insertion limits (Low-Low Alarm to ensure adequate shutdown in the event of a reactor trip, to ensure that maximum possible ejected rod reactivity
limits are maintained
and to ensure acceptable
core power distributions.
I.Before withdrawing
any rod bank from the fully inserted position, the group step counters and the rod position indicators
for that bank must be at zero steps.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 7 of 77 3.0 PRECAUTIONS
AND LIMITATIONS (Continued)
J.Deleted K.The Control Rods shall NOT be stepped or tripped unless the RCS pressure is at least 1 00 psig.L.RPls and step counters shall be maintained
within limits per TS 3.1.3.1 and 3.1.3.2.M.Continuous
rod motion shall comply with these restrictions:
CRDM OUTLET ROD MOTION LIMITS TEMPERATURE190&deg;F 10 minutes ON 20 minutes OFF200&deg;F 6 minutes ON 24 minutes OFF Time limitations
are due to a lower air flow rate of 48,000 cfm across the shroud combined with a higher temperature (Reference
TSIR-97-80P-30-636
and Westinghouse
Letters RIM's#838931005806, 838930920800, and 838931005803).
N.The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation
or indication:
1)Hand switch failure;2)relay failure, and 3)failure of both 100v DC power supplies (PS3 and PS6)simultaneously.
O.Defeating or restoring Tavg/Delta
T or NIS channel may cause step change in input to rod control.A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 8 of 77 3.0 PRECAUTIONS
AND LIMITATIONS (Continued)
P.Directional
Overcurrent
Relay Targets are reset by depressing
the Relay Target Reset Pushbutton
on the panel to break the target coil seal in circuit and then lifting the mechanical
reset at the bottom of the relay cover.Q.US/SRO Oversight for control rod manipulation
shall include:1.Prior to Rod Movement a.Ensure RPI's within T.S.range (+or-12 steps)b.Ensure delta flux will not be adversely affected c.Ensure Tavg and Rx Thermal power will not be adversely affected d.Verify on target with Rx Eng reactivity
balance sheet e.Verify power change will not exceed hourly rate f.Ensure no simultaneous
reactivity
manipulations
in progress (i.e.: borations, dilutions or turbine load changes)2.During Rod Movement a.Ensure RO has peer check b.Ensure RO is following procedure c.Ensure RO understands
how many steps they are moving rods d.Ensure RO has checked all the above mentioned items e.Watch performance
of rod manipulation
while listening to audible indication
of rod step f.Ensure peer check is doing their job g.Re-verify stepsa-d of initial evaluation
h.Ensure procedure is followed placing rods back to auto (Tavg-Tref mismatch)i.Monitor plant for expected response
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 9 of 77 UnitJ_4.0 PREREQUISITE
ACTIONS Date Q'Ix 7/987;NOTE Throughout
this instruction
where an IF/THEN statement occurs, the step may be N/A if the condition does NOT exist.[1]ENSURE the instruction
to be used is a copy of the effective version.[2]ENSURE Precautions
and Limitations, Section 3.0 has been reviewed.[3]ENSURE each performer documents their name and initials: WtA Print Name Initials W tJSoN'-r: A bbu+w7A[4]INDICATE below which performance
section of this instruction
will be used and the reason for this performance:
D 5.0 STARTUP/STANDBY
READINESS ff.6.0 NORMAL OPERATION D 7.0 SHUTDOWN D 8.0 INFREQUENT
OPERATION Reason: WI'1Hb/t4W
t3AN(P{LI\l(l To (2t A(:10 r'l s"1 A(l:1 U f
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 10 of 77 Unit Date_5.0 STARTUP/STANDBY
READINESS 5.1 Placing MG Set(s)in Standby Readiness[1]ENSURE Section 4.0, Prerequisites
complete.[2]ENSURE[HS-85-5110], Rod Control Mode Selector Switch is in the MANUAL position.[3]IF performance
is on Unit 1, THEN ENSURE Power Checklist 1-85-1.01 is complete.[4]IF performance
is on Unit 2, THEN ENSURE Power Checklist 2-85-1.01 is complete.NOTE Green targets on the breaker handswitches
can be obtained by rotating the operating switch to the TRIP position and releasing to the NEUTRAL position.[5]ENSURE the following breakers are in the required position: BREAKER REQUIRED TARGET INITIALS POSITION COLOR CRD MG SetA OPEN GREEN Motor Bkr 52A (480V Unit Bd)CRD MG Set B OPEN GREEN Motor Bkr 52B (480V Unit Bd)MG SetA OPEN GREEN Load (Generator)
Bkr 52-1 MG Set B OPEN GREEN Load (Generator)
Bkr 52-2[6]VERIFY[XA-55-4B-A5], ROD CONTROL MG SETS TRIPPED OR GROUNDED, alarm is NOT LIT.D D D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 11 of 77 UNIT Date_5.1 Placing MG Set(s)in Standby Readiness (Continued)
[7]TURN Generator No.1 Westinghouse
Thyrex Voltage Regulator (Reg)potentiometer
to the FULL COUNTER-CLOCKWISE
position and RETURN to the 9 O'CLOCK position.[8]TURN Generator No.2 Westinghouse
Thyrex Voltage Regulator (WTV Reg)potentiometer
to the FULL COUNTER-CLOCKWISE
position and RETURN to the 9 O'CLOCK position.[9]ENSURE the following MG Set handswitches
are in the required position: SWITCH REQUIRED INITIALS POSITION MG Set A Ammeter Selector Switch A MG Set B Ammeter Selector Switch A MG Set A Voltmeter Selector Switch AB MG Set B Voltmeter Selector Switch AB Generator No.1 Synchronize
Sel Sw OFF Generator No.2 Synchronize
Sel Sw OFF[10]ENSURE[1 KS], Three Pole Grounding Switch (located inside L-115 cabinet)is in the OPEN position.[11]ENSURE all relays and targets (located on L-115)for the MG Set breakers are RESET.End of Section 5.1
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 12 of 77 Unit Date----5.1.1 Placing MG Set A In Service With MG Set B Not Operating[1]ENSURE MG Set A is in Standby Readiness.
[2]START CRD MG Set A by placing[HS-85-1A]
MOTOR Breaker 52A Circuit Control in the CLOSE position.D D NOTE Allow 15 seconds for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.
[a]WHEN generator has increased to full speed, THEN[b]DEPRESS AND HOLD Gen Field Flash pushbutton.
[c]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.
[4]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with wrv Reg to a nominal 260 volts.D D D D NOTE Voltage may vary slightly between phases.[5]CHECK equal voltage on all phases using voltmeter selector switch.D NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[6]ENSURE MG Set A Load (GENERATOR)
Breaker 52-1[BCTF-85-121
is RACKED IN.
SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 13 of 77 Unit Date_5.1.1 Placing MG Set A In Service With MG Set B Not Operating (Continued)
[7]ENSURE MG Set B Load (GENERATOR)
Breaker 52-2[BCTF-85-22]
is RACKED IN.[8]ENSURE CRDM MG Set A Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al
(67 A)[1-RL Y-085-DE/4D/C]
(67C)[2-RLY-085-DG/4D/A]
(67 A)[2-RL Y-085-DG/4D/C]
(67C)[9]ENSURE targets for CRDM MG Set A Directional
Overcurrent
Relays RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]
(67 A)[1-RL Y-085-DE/4D/C]
(67C)[2-RL Y-085-DG/4D/A]
(67 A)[2-RL Y-085-DG/4D/C]
(67C)NOTE: Generator voltage will drop slightly as the electrical
load increases.
[10]CLOSE MG Set A Load (GENERATOR)
Breaker 52-1 USING[HS-85-121.
[11]IF MG Set A Load breaker 52-1 trips due to Directional
Overcurrent
Relay operation, THEN[a]RESET Directional
Overcurrent
Relays with Relay Target Reset Button on Relay panel.[b]RESET Directional
Overcurrent
Relay Targets.[c]RECLOSE MG Set A load Breaker 52-1 USING[HS-85-121.
D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 14 of 77 Unit Date_5.1.1 Placing MG Set A In Service With MG Set B Not Operating (Continued)
[d]IF another trip of breaker 52-1 occurs, REPEAT substeps[a],[b]and[c].[e]IF breaker 52-1 trips the third time, THEN NOTIFY SM and System Engineering
for assistance.
[12]WHEN placing the MG Sets in service initially OR Reactor Trip Breakers are to be reset, THEN GO TO Section 5.2, Resetting Reactor Trip Breakers.End of Section 5.1.1 D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 15 of 77 Date_Placing MG Set B In Service With MG Set A Not Operating Unit------5.1.2[1]ENSURE MG Set B is in Standby Readiness.
D[2]START CRD MG Set B by placing[HS-85-1 B]MOTOR Breaker 52B Circuit Control in the CLOSE position.D NOTE Allow 15 seconds for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.
D[4]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.
D[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.
D[5]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts.D NOTE Voltage may vary slightly between phases.[6]CHECK equal voltage on all phases using voltmeter selector switch.D NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[7]ENSURE MG Set A Load (GENERATOR)
Breaker 52-1 is RACKED IN.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 16 of 77 Unit Date_5.1.2 Placing MG Set B In Service With MG Set A Not Operating (Continued)
[8]ENSURE MG Set B Load (GENERATOR)
Breaker 52-2 is RACKED IN.[9]ENSURE CRDM MG Set B Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/A]
(67 A)[1-RLY-085-DF/3B/C]
(67C)[2-RL Y-085-DH/3B/A]
(67 A)[2-RL Y-085-DH/3B/C]
(67C)[10]ENSURE targets for CRDM MG Set B Directional
Overcurrent
Relays are RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al
(67 A)[1-RLY-085-DF/3B/C]
(67C)[2-RL Y-085-DH/3B/A]
(67 A)[2-RL Y-085-DH/3B/C]
(67C)NOTE Generator voltage will drop slightly as the electrical
load increases.
[11]CLOSE MG Set B Load (GENERATOR)
Breaker 52-2 USING[HS-85-22].
[12]IF MG Set B Load breaker 52-2 trips due to Directional
Overcurrent
Relay operation, THEN[a]RESET Directional
Overcurrent
Relays with Relay Target Reset Button on Relay panel.[b]RESET Directional
Overcurrent
Relay Targets.[c]RECLOSE MG Set B load Breaker 52-2 USING[HS-85-221.
D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 17 of 77 Unit Date_5.1.2 Placing MG Set B In Service With MG Set A Not Operating (Continued)
[d]IF another trip of breaker 52-2 occurs, REPEAT substeps[a],[b]and[c].[e]IF breaker 52-2 trips the third time, THEN NOTIFY SM and system engineering
for assistance.
[13]WHEN placing the MG Sets in service initially OR Reactor Trip Breakers are to be reset, THEN GO TO Section 5.2, Resetting Reactor Trip Breakers.End of Section 5.1.2 D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 18 of 77 unitl_5.2 Reset/Close
Reactor Trip Breakers[1]ENSURE desired MG Set is In Service.[2]ENSURE[1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED.(located in Panel L-115).[3]ENSURE lift coil disconnect
switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).[4]ENSURE all Control Rods and Shutdown Rods are inserted: ROD BANK FULLY INSERTED (-V)Shutdown Bank A[3'Shutdown Bank BShutdown Bank CShutdown Bank DControl Bank AControl Bank B CH'Control Bank CControl Bank DWTA W-rA CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[5]MOMENTARILY
PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY RPls and group step counters are at zero steps.W'tA
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 19 of 77 Unit Date 0#/oS/5.2 Reset/Close
Reactor Trip Breakers (Continued)
[6]ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT.BYPASS OPENRACKED OUT BREAKERBYA[}1'.-BYB cV cY[7]ENSURE Reactor Trip breakers are RACKED IN: TRIP BREAKER RTA RTB RACKED IN (..J)[8]ENSURE control power is ON by GREEN indicating
lights on M-4: BREAKER GREEN POSITION LIGHT INITIALS INDICATION
RTA ON UJ1tl RTB ON tAJflf[9]ENSURE Rod Control switch[HS-85-51111
is in MID position.[10]IF unit is in Mode 3,THEN ENSURE requirements
of Tech Spec 3.4.1.2 are met.[11]DEPRESS and HOLD FW Isol Reset pushbuttons
[HS-3-99A]
and[HS-3-99B].
[C.1]W10
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 20 of 77 I Unit------5.2 Reset/Close
Reactor Trip Breakers (Continued)
[12]IF resetting Unit 1 Reactor Trip Breakers, THEN CLOSE Rx Trip Breakers by placing[1-RT-1], in CLOSE position.[13]IF resetting Unit 2 Reactor Trip Breakers, THEN CLOSE Rx Trip Breakers by placing[2-HS-99-7], in CLOSE position.[14]VERIFY Reactor Trip Breakers CLOSED by RED indicating
lights on M-4: BREAKER POSITION RED LIGHT INITIALS INDICATION
RTA ON VV-rtt RTB ON W<1A[15]RELEASE FW Isol Reset push buttons[HS-3-99A]
and[HS-3-99B].
[C.1][16]NOTIFY IMs to perform 1,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts.[17]IF Shutdown or Control Rods will be withdrawn, THEN GO TO Section 6.3, Manual Operation of Rod Control System Below 15 Percent Power.End of Section 5.2 Date 0 J/xx,lo3
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 21 of 77 Unit Date----6.0 NORMAL OPERATION 6.1 Placing MG Set A In Service With MG Set B Operating[1]ENSURE MG Set B is In Service.[2]ENSURE MG Set A is in Standby Readiness.
D[3]ENSURE Reactor Trip Breakers are CLOSED.[4]START CRD MG Set A by placing[HS-85-1Al
MOTOR Breaker 52A Circuit Control in the CLOSE position.D[5]VERIFY generator speed increasing.
D[6]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.
D[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.
D NOTE Digital voltmeters
are much more accurate than panel meters and are the preferred instrumentation
when synchronizing
the generators.
The panel meters should only be used in the event of an emergency.
[7]REQUEST the SM/SRO to determine which of the following types of meters should be used to synchronize
and balance the MG Sets: MG Set panel meters.D Digital meters.D US/SRO
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 22 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
NOTE The auto synchronizing
circuit has a low voltage cutout circuit which will NOT allow the second MG Set to synchronize
if voltage on the loaded MG Set is less than 254 volts.Minimum voltage for placing the second generator in parallel is 260 volts.[8]IF using the MG Set panel voltmeters
for voltage adjustment, THEN[a]ENSURE MG Set B voltage is ADJUSTED with Westinghouse
Thyrex voltage (WTV)regulator potentiometer
to 260 volts (within plus or minus 1.0 volts)on panel meter.[b]ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer
to match MG Set B voltage.CAUTION Do NOT jar MG set panel doors when they are being opened or closed.There is a potential for inadvertent
relay operation.
[9]IF using digital meters for voltage adjustment, THEN[a]ENSURE qualified electrical
maintenance
personnel have OBTAINED 2 Fluke 8840A (or equivalent)
digital voltmeters
and 2 Keithley 197 (or equivalent)
digital voltmeters
to be used for synchronization
and balancing of the MG Sets.[b]ENSURE Keithley (or equivalent)
digital voltmeters (DVM)are CONNECTED to the terminals on the panel voltmeters
for both MG Set Band MG Set A.This DVM voltage is proportional
to generator voltage.[c]ENSURE Fluke (or equivalent)
digital voltmeters (DVM)are CONNECTED to the terminals on the panel ammeters for both MG Set Band MG Set A.This DVM voltage is proportional
to generator amps.(Step continued on Next Page)
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 23 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
[9](Continued)
[d]ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer
to 108 volts (260 volts on panel meter)as indicated on the digital voltmeter, to be within plus or minus 1.0 volt (digital voltmeter).
[e]ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer
to match MG Set B voltage, to be within 0.5 volts (digital voltmeter).
[10]ENSURE CRDM MG Set A Directional
Overcurrent
Relay Target Coils RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]
(67 A)[1-RL Y-085-DE/4D/Cl
(67C)[2-RL Y-085-DG/4DI
A](67 A)[2-RL Y-085-DG/4D/Cl
(67C)[11]ENSURE targets for CRDM MG Set A Directional
Overcurrent
Relays RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al
(67 A)[1-RL Y-085-DE/4D/C]
(67C)[2-RL Y-085-DG/4D/A]
(67 A)[2-RL Y-085-DG/4D/C]
(67C)NOTE The following step should close the generator load breaker if paralleling
is successful.
[12]PLACE[HS-85-12Bl
Gen NO.1 SYNCHRONIZE
Switch in the ON position.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 24 of 77 Unit Date_6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
NOTE MG Set A should parallel within 17 seconds.[13]IF MG Sets are paralleled, THEN[a]PLACE[HS-85-12B]
Gen NO.1 SYNCHRONIZE
Switch in the OFF position.[14]IF DVMs are being utilized to balance generator amps (loading), THEN PERFORM the following to balance MG setA&B currents:[a]RECORD"as found" voltage and current readings: NOTE With MG sets paralleled, the voltmeters
are reading the same electrical
point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 25 of 77 Unit Date_6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
[14](Continued)
[a](Continued)
NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical
point.Therefore, data is required from 80TH MG sets in sub-steps7-12.7.ENSURE MG Set A and 8 Ammeter Selector Switches are selected for"A".8.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected tothepanel amp meters for: MG SetA mV------MG Set 8 mV 9.ENSURE MG Set A and 8 Ammeter Selector Switches are selected for"8".10.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set 8 mV 11.ENSURE MG Set A and 8 Voltmeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set 8 mV[b]EVALUATE'as found" data from Step[14][a]and the position of thedirectionalcontacts
on the Directional
Overcurrent
Relays (DaR)associated
with both MG sets to determine if any adjustment
is necessary.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 26 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
[14](Continued)
NOTE There are two methods by which balanced MG Set currents can be achieved using the WTV Voltage Potentiometers.
The preferred method is to balance the Directional
Overcurrent
Relaysdirectionalcontacts
to the far right and as steady as achievable
while maintaining
108+/-1 volts on the Fluke (or equivalent)
DVMs connected to the MG Set voltmeters.
This method will NOT usually result in currents balanced to within 1 mV (as read on the Keithley (or equivalent)).
The secondary method is to balance the Keithley (or equivalent)DVMsconnected
to the panel ammeters to within 1 mV while maintaining
108+/-1 volts as indicated by the Fluke (or equivalent)
DVM connected to the generator voltmeter.
[c]IF adjustment
is determined
to be necessary by Cognizant Craft or Engineer, THEN ADJUST WTV voltage regulator potentiometers
on MG SetsA&B to balance generator currents.[d]IF an adjustment
was made, THEN RECORD"as left" voltage and current readings: NOTE With MG sets paralleled, the voltmeters
are reading the same electrical
point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 27 of 77 Unit Date_6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
[14](Continued)
[d](Continued)
4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected tothepanel volt meters for: MG Set A OR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical
point.Therefore, data is required from BOTH MG sets in sub-steps7-12.7.ENSURE MG Set A and B Ammeter Selector Switches are selected for"A".8.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV 9.ENSURE MG Set A and B Ammeter Selector Switches are selected for"B".1 O.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 28 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
[14](Continued)
[d](Continued)
11.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV-----MG Set B mV[e]IF digital meters were installed in step[9], THEN 1.ENSURE all digital meters are removed.2.ENSURE the MG Set panel doors are closed.[15]IF MG Set A load breaker 52-1 closes but subsequently
trips due to Directional
Overcurrent
Relay operation, THEN[a]PLACE[HS-85-12Bl
Gen NO.1 SYNCHRONIZE
Switch in the OFF position.[b]ENSURE CRDM MG Set A Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al
(67 A)[1-RL Y-085-DE/4D/C]
(67C)[2-RLY-085-DG/4D/Al
(67 A)[2-RL Y-085-DG/4D/Cl
(67C)__I_-1st CV 1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 29 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)
[c]ENSURE targets for CRDM MG Set A Directional
Overcurrent
Relays RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]
(67 A)[1-RL Y-085-DE/4D/Cl
(67C)[2-RLY-085-DG/4D/Al
(67 A)[2-RL Y-085-DG/4D/Cl
(67C)[d]IF 1 st attempt to synchronize, RETURN to step[12].[e]IF 2 nd attempt to synchronize
was unsuccessful, THEN INITIATE a WO to troubleshoot
the problem.[16]IF MG Set A does NOT parallel within 17 seconds, THEN[a]CHECK MG Set voltages.[b]IF voltages appear to have drifted apart AND/OR another adjustment
is desired, THEN D D D 1.2.PLACE[HS-85-12Bl
Gen No.1 SYNCHRONIZE
Switch in the OFF position.RETURN to step[7].D D[17]IF Alternate Method of Paralleling
MG Set A is desired, THEN GO TO Section 8.1.[18]ENSURE target for CRD MG Set A Load (GENERATOR)
Bkr 52-1 is RED by placing[HS-85-121
GENERATOR breaker circuit control in the CLOSE position.End of Section 6.1 D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 30 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating[1]ENSURE MG Set A is In Service.D[2]ENSURE MG Set B is in Standby Readiness.
D[3]ENSURE Reactor Trip Breakers are CLOSED.D[4]ST ART CRD MG Set B by placing fHS-85-1 B]MOTOR Breaker 52B Circuit Control in the CLOSE position.D[5]VERIFY generator speed increasing.
D[6]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.
D[b]WHEN voltage is greater than 250 volts, THEN RELEASE Gen Field Flash pushbutton.
D NOTE Digital voltmeters
are much more accurate than panel meters and are the preferred instrumentation
when synchronizing
the generators.
The panel meters should only be used in the event of an emergency.
[7]REQUEST the SM/SRO to determine which of the following types of meters should be used to synchronize
and balance the MG Sets: MG Set panel meters.D Digital meters.D SM/SRO
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2.Rev 32 Page 31 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
NOTE The auto synchronizing
circuit has a low voltage cutout circuit which will NOT allow the second MG Set to synchronize
if voltage on the loaded MG Set is less than 254 volts.Minimum voltage for placing the second generator in parallel is 260 volts.[8]IF using the MG Set panel voltmeters
for voltage adjustment, THEN[a]ENSURE MG Set A voltage is ADJUSTED with Westinghouse
Thyrex voltage (WTV)regulator potentiometer
to 260 volts (within plus or minus 1.0 volts)on panel meter.[b]ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer
to match MG Set A voltage.CAUTION Do NOT jar MG set panel doors when they are being opened or closed.There is a potential for inadvertent
relay operation.
[9]IF using digital meters for voltage adjustment, THEN[a]ENSURE qualified electrical
maintenance
personnel have OBTAINED 2 Fluke 8840A (or equivalent)
digital voltmeters
and 2 Keithley 197 (or equivalent)
digital voltmeters
to be used for synchronization
and balancing of the MG Sets.[b]ENSURE Keithley (or equivalent)
digital voltmeters (DVM)are CONNECTED to the terminals on the panel voltmeters
for both MG Set Band MG Set A.This DVM voltage is proportional
to generator voltage.[c]ENSURE Fluke (or equivalent)
digital voltmeters (DVM)are CONNECTED to the terminals on the panel ammeters for both MG Set Band MG Set A.This DVM voltage is proportional
to generator amps.(Step continued on Next Page)
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 32 of 77 Unit Date_6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[d]ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer
to 108 volts (260 volts on panel meter)as indicated on the digital voltmeter, to be within plus or minus 1.0 volt (DVM).[e]ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer
to match MG Set A voltage, to be within 0.5 volts (DVM).[10]ENSURE CRDM MG Set B Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/A]
(67 A)[1-RLY-085-DF/3B/C]
(67C)[2-RL Y-085-DH/3B/Al
(67 A)[2-RL Y-085-DH/3B/Cl
(67C)re ay.o er nl Relay INITIALS[1-RL Y-085-DF/3B/Al
(67 A)[1-RLY-085-DF/3B/Cl
(67C)[2-RL Y-085-DH/3B/Al
(67 A)[2-RL Y-085-DH/3B/Cl
(67C)[11]ENSURE targets for CRDM MG Set B Directional
Overcurrent
Relays are RESET (Mechanical
Linkage onI)(N/A th U't)NOTE The followingstepshould
close the generator load breaker if paralleling
is successful.
[12]PLACE[HS-85-22B]
Gen NO.2 SYNCHRONIZE
Switch in the ON position.NOTE MG Set B should parallel within 17 seconds.[13]IF MG Sets are paralleled, THEN[a]PLACE[HS-85-22B]
Gen NO.2 SYNCHRONIZE
Switch in the OFF position.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 33 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[14]IF DVMs are being utilized to balance generator amps (loading), THEN PERFORM the following to balance MG setA&B currents:[a]RECORD"as found" voltage and current readings: NOTE With MG sets paralleled, the voltmeters
are reading the same electrical
point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORDoneMG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG SetAOR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORDoneMG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG SetAOR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical
point.Therefore, data is required from BOTH MG sets in sub-steps7-12.7.ENSURE MG Set A and B Ammeter Selector Switches are selected for"A".
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 34 of 77 Unit Date_6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[14](Continued)
[a](Continued)
8.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected tothepanel amp meters for: MG SetA mV------MG Set B mV 9.ENSURE MG Set A and B Ammeter Selector Switches are selected for"B".1 O.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV 11.ENSURE MG Set A and B Ammeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV[b]EVALUATE'as found" data from Step[14][a]and the position of the directional
contacts on the Directional
Overcurrent
Relays (DOR)associated
with both MG sets to determine if any adjustment
is necessary.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 35 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[14](Continued)
NOTE There are two methods by which balanced MG Set currents can be achieved using the WTV Voltage Potentiometers.
The preferred method is to balance the Directional
Overcurrent
Relays directional
contacts to the far right and as steady as achievable
while maintaining
108+/-2 volts on the Fluke (or equivalent)
DVMs connected to the MG Set voltmeters.
This method will NOT usually result in currents balanced to within 1 mV (as read on the Keithley (or equivalent)).
The secondary method is to balance the Keithley (or equivalent)
DVMs connected to the panel ammeters to within 1 mV while maintaining
108+/-1 volts as indicated by the Fluke (or equivalent)
DVM connected to the generator voltmeter.
[c]IF adjustment
is determined
to be necessary by Cognizant Craft or Engineer, THEN ADJUST WTV voltage regulator potentiometers
on MG SetsA&B to balance generator currents.[d]IF an adjustment
was made, THEN RECORD"as left" voltage and current readings: NOTE With MG sets paralleled, the voltmeters
are reading the same electrical
point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 36 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[14](Continued)
[d](Continued)
4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)
DVM connected to the panel volt meters for: MG Set A OR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical
point.Therefore, data is required from BOTH MG sets in sub-steps7-12.7.ENSURE MG Set A and B Ammeter Selector Switches are selected for"A".8.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV 9.ENSURE MG Set A and B Ammeter Selector Switches are selected for"B".10.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 37 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[14](Continued)
[d](Continued)
11.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)
DVM connected to the panel amp meters for: MG SetA mV-----MG Set B mV[e]IF digital meters were installed instep[9], THEN 1.ENSURE all digital meters are removed.__I_-1st CV 2.ENSURE the MG Set panel doors are closed.[15]IF MG Set B load breaker 52-2 closes but subsequently
trips due to Directional
Overcurrent
Relay operation, THEN[a]PLACE[HS-85-22Bl
Gen NO.2 SYNCHRONIZE
Switch in the OFF position.[b]ENSURE CRDM MG Set B Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al
(67 A)[1-RLY-085-DF/3B/C]
(67C)[2-RL Y-085-DH/3B/Al
(67 A)[2-RL Y-085-DH/3B/C]
(67C)1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 38 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)
[c]ENSURE targets for CRDM MG Set B Directional
Overcurrent
Relays are RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al
(67 A)[1-RLY-085-DF/3B/Cl
(67C)[2-RL Y-085-DH/3B/Al
(67 A)[2-RL Y-085-DH/3B/Cl
(67C),[d]IF 1 st attempt to synchronize, RETURN to step[12].[e]IF 2 nd attempt to re-synchronize
was unsuccessful, THEN INITIATE a WO to troubleshoot
the problem.[16]IF MG Set B does NOT parallel within 17 seconds, THEN[a]CHECK MG Set voltages.[b]IF voltages appear to have drifted apart AND/OR another adjustment
is desired, THEN 1.PLACE[HS-85-22Bl
Gen NO.2 SYNCHRONIZE
Switch in the OFF position.2.RETURN to step[7].[17]IF Alternate Method of Paralleling
MG Set B is desired, THEN GO TO Section 8.2.[18]ENSURE target for CRD MG Set B Load (GENERATOR)
Bkr 52-2 is RED by placing[HS-85-22]
GENERATOR breaker circuit control in the CLOSE position.End of Section 6.2 D D D D D D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 39 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power CAUTION If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50&deg;F is planned, the shutdown and control banks should be withdrawn at least 5 steps each.This will limit the possibility
of"thermal lock-up" of the rods.Thermal lock-up is NOT a concern during unit heatup.NOTE Continuous
rod motion shall comply with these restrictions:
CRDM OUTLET ROD MOTION LIMITS TEMPERATURE
s190&deg;F 10 minutes ON 20 minutes OFF s200&deg;F 6 minutes ON 24 minutes OFF[1]ENSURE Section 5.2, ReseUClose
Reactor Trip Breakers has been completed.
[2]IF the shutdown and control rods were withdrawn 5 steps to prevent thermal lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawal.
D 1st CV NOTE CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)Resets: A.All GROUP STEP COUNTERS on the Control Board.B.The master cycler reversible
counter.C.All slave cycler counters.D.The bank overlap counter.E.All internal memory and alarm circuits.F.All pulse-to-analog
converters
in the Rod Position Indication
System.ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[3]MOMENTARILY
PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System.D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 40 of 77 Unit Oate_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
CAUTION Before withdrawing
any rod from the fully inserted position, all Group Step Counters and all Rod Position indicators
must be at zero steps.[4]ENSURE all Full Length Rod step counters reset to zero.[5]VERIFY rod control IN-OUT direction lights are NOT LIT.[6]DEPRESS[RCAS], Rod Urgent Failure Alarm Reset.[7]RESET Window 6 (A-6), ROD CONTROL SYSTEM URGENT FAILURE alarm on panel[XA-55-4Bl
using[XS-55-4A], Annunciator
RESET/ACKITEST
Switch.[8]VERIFY the following rod control system alarms on panel[XA-55-4Bl
are NOT LIT: WINDOW NOT LIT NUMBER N)5 (A5)D 6 (A6)D 11 (84)D 12 (85)D 13(86)D 18 (C4)D 19(C5)D 27 (06)D 34 (E6)D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 41 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[9]ENSURE Plant computer points for rod bank position are ZERO using the following computer points: COMPUTER PT ROD BANK..J U0049 Control A D U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D U0056 Shutdown D D[10]MONITOR Control Rod position USING Rod Position Indicators
ICS screen 30 minute trend during SD&Control Banks withdrawal
to aid in detecting rod misalignment.
D[11]IF Individual
Rod Position Indication
does not indicate proper rod position during withdrawal
of SD Banks, THEN[a]STOP rod withdrawal.
D[b]ENSURE subcriticality.
D[c]CONTACT MIG AND INITIATE troubleshooting.
D[d]IF troubleshooting
does not resolve the problem, OR subcriticality
can NOT be verified, THEN INITIATE Reactor TRIP.D[12]IF Individual
Rod Position Indication
does not indicate proper rod position during withdrawal
of Control Banks, THEN GO TO AOP-C.01 section 2.6 Rod Position Indicator (RPI)Malfunction
-Modes 1 or 2.D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 42 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
CAUTION NOTE 1 Under normal conditions
control rod banks must be withdrawn and inserted in the prescribed
sequence.For withdrawal, the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank 0, Control Bank A, Control Bank B, Control Bank C, Control Bank D.The insertion sequence is the reverse of the withdrawal
sequence.Startup rate, Source range, Intermediate
range, Nuclear Instrumentation
recorders, Group Step Counters and the Rod Position Indicators
should be monitored during each bank withdrawal.
NOTE 2 The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation
or indication:
1)Hand switch failure;2)relay failure, and 3)simultaneous
failure of both 100v DC power supplies (PS3 and PS6)[13]PLACE[HS-85-511
0], Rod Control Mode Selector to the SBA position.1st CV[14]VERIFY Rod Speed Indicator[SI-412], indicates 64 Steps/minute.
1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 43 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
NOTE Monitor Group Step Counters, Rod Position Indicator and the"IN-OUT" status lights to ensure anticipated
motion as each bank is being withdrawn.
Rod speed indicator should be reading 64 steps per minute.[15]ENSURE Shutdown Bank A demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Shutdown Bank A one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111
to withdraw Shutdown Bank A one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank A fully INSERTED.D 2.RETURN to beginning of this step.D NOTE The fully withdrawn position for shutdown and control rods is defined by TI-28, Att.6.[16]WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN position using[HS-85-5111].
1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 44 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[17]PLACE[HS-85-511
01, Rod Control Mode Selector to the SBB position.1st CV[18]VERIFY Rod Speed Indicator[SI-412], indicates 64 Steps/minute.
__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation
or indication:
1)Hand switch failure;2)relay failure, and 3)simultaneous
failure of both 100v DC power supplies (PS3 and PS6).[19]ENSURE Shutdown Bank B demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Shutdown Bank B one-half step at a time, for one full step.1 st cv[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-5111]
to withdraw Shutdown Bank B one-half step at a time, for the second full step.1st cv[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank B fully INSERTED and D 2.RETURN to beginning of this step.D[20]WITHDRAW Shutdown Bank B to the FULL Y WITHDRAWN position using[HS-85-5111].
1st cv
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 45 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[21]PLACE[HS-85-511
0], Rod Control Mode Selector to the SBC position.1st CV[22]VERIFY Rod Speed Indicator[SI-412], indicates o Steps/minute.
__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation
or indication:
1)Hand switch failure;2)relay failure, and 3)simultaneous
failure of both 100v DC power supplies (PS3 and PS6).[23]ENSURE Shutdown Bank C demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Shutdown Bank C one full step.1st CV[b]CHECK group demand position counter advances properly.D[c]BUMP[HS-85-5111]
to withdraw Shutdown Bank C a second full step.1st CV[d]VERIFY group demand position counter advanced properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank C fully INSERTED and D 2.RETURN to beginning of this step.D[24]WITHDRAW Shutdown Bank C to the FULLY WITHDRAWN position using[HS-85-51111.
1 st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 46 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[25]PLACE[HS-85-511
0], Rod Control Mode Selector to the SBD position.1st CV[26]VERIFY Rod Speed Indicator[SI-412], indicates o Steps/minute.
__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation
or indication:
1)Hand switch failure;2)relay failure, and 3)simultaneous
failure of both 100v DC power supplies (PS3 and PS6).[27]ENSURE Shutdown Bank D demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Shutdown Bank D one full step.1 st CV[b]CHECK group demand position counter advances properly.D[c]BUMP[HS-85-51111
to withdraw Shutdown Bank D a second full step.1st CV[d]VERIFY group demand position counter advanced properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank D fully INSERTED and D 2.RETURN to beginning of this step.D[28]WITHDRAW Shutdown Bank D to the FULL Y WITHDRAWN position using[HS-85-5111
1.1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 47 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
NOTE Remainder of this section performed in conjunction
with 0-GO-2 or 0-RT-NUC-000-003.0.
[29]PLACE[HS-85-511
0], Rod Control Mode Selector to the MANUAL position.1st CV[30]VERIFY Rod Speed Indicator[SI-412], indicates 48 Steps/minute.
__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation
or indication:
1)Hand switch failure;2)relay failure, and 3)simultaneous
failure of both 100v DC power supplies (PS3 and PS6).[31]ENSURE Control Bank A demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Control Bank A one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-5111]
to withdraw Control Bank A one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank A fully INSERTED and D 2.RETURN to beginning of this step.D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 48 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[32]CONTINUE withdrawal
of Control Bank A using[HS-85-5111], Rod Control Switch to 128 steps or next doubling.NOTE When Control Bank A is above 20 steps, alarm FULL LENGTH RODS AT BOTTOM light on[XA-55-4B]
should clear.When Control Bank A gets above 20 steps and rods are driven back in, the alarm will come back in.When Control Banks B, C, and 0 get above 35 steps, then drop below 20 steps, the alarm will come back in.[33]WHEN Control Bank A is above 20 steps, THEN ENSURE Window 28 (0-7), FULL LENGTH RODS RODS AT BOTTOM alarm on panel[XA-55-4B]
CLEARS.
SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 49 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
CAUTION When Control Bank A is reaches 128 steps, Control Bank B should begin to move.Each successive
bank should begin to move when the previous bank reaches 128 steps.[34]WHEN Control Bank A is withdrawn to 128 steps, THEN ENSURE Control Bank B demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Control Bank B one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111
to withdraw Control Bank B one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank B fully INSERTED and D 2.RETURN to beginning of this step.D[35]CONTINUE withdrawal
of Control Bank Busing[HS-85-5111l
to 128 steps or next doubling.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 50 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[36]WHEN Control Bank B is withdrawn to 128 steps, THEN ENSURE Control Bank C dema,nd position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Control Bank C one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111
to withdraw Control Bank C one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank C fully INSERTED and D 2.RETURN to beginning of this step.D[37]CONTINUE withdrawal
of Control Bank C using[HS-85-51111
to 128 steps or next doubling.NOTE Three steps are added to the low-low insertion limit (110 steps@zero power)until LEFM is available.
[38]WHEN Control Bank C is113 Steps, THEN ENSURE Window 14 (B-7), ROD CONTROL BANKS LIMIT LOW-LOW alarm on panel[XA-55-4Bl
CLEARS.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 51 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
NOTE Three steps are added to the low insertion limit (120 steps@zero power)until LEFM is available.
[39]WHEN Control Bank C is123 steps, THEN ENSURE Window 7 (A-7), ROD CONTROL BANKS LIMIT LOW alarm on panel[XA-55-4Bl
CLEARS.[40]WHEN Control Bank C is withdrawn to 128 steps, THEN ENSURE Control Bank 0 demand position counters operational
by performing
the following:
[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Control Bank 0 one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111
to withdraw Control Bank 0 one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.
D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank D fully INSERTED and D 2.RETURN to beginning of this step.D[41]CONTINUE withdrawal
of Control Bank Dusing[HS-85-51111
to next doubling or criticality.
End of Section 6.3
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 52 of 77 Unit Date----6.4 Transferring
from Manual to Auto Rod Control NOTE 1 NOTE 2 NOTE 3 A laminated copy of this section can be maintained
in the Unit Control Room for repetitive
use for routine rod manipulations.
Defeating or restoring Tavg/Delta
T or NIS channel may cause step change in input to rod control.A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.This Section may be N/A if Rod Control is being returned to AUTO in response to a transient (runback)condition.
[1]ENSURE turbine power is greater than 15 percent.[2]ENSURE Window 31 (E-3), LOW TURB IMPULSE PRESS ROD WITHDRAWAL
BLOCKED C-5, Permissive
light on panel[XA-55-4A]
is NOT LIT.[3]ENSURE lessthan1 degree Tavg/Tref mismatch.[4]PLACE[HS-85-511
0], Rod Control Mode Selector in the AUTO position.1st cv[5]VERIFY Rod Speed Indicator[SI-412], indicates 8 Steps/minute.
1 st CV End of Section 6.4
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 53 of 77 Unit Date_6.5 Transferring
from Auto to Manual Rod Control NOTE 1 A laminated copy of this section can be maintained
in the Unit Control Room for repetitive
use for routine rod manipulations.
NOTE 2 Manual rod withdrawal
is inhibited by any of the following signals: A.C-1, High Flux Intermediate
Range Monitor B.C-2, High Flux Power Range Monitor C.C-3, Overtemperature
Delta-T D.C-4, Overpower Delta-T[1]PLACE[HS-85-5110], Rod Control Mode Selector in the MANUAL position.[2]VERIFY Rod Speed Indicator[SI-412], indicates 48 Steps/minute.
[3]IF control rod movement is required, THEN ADJUST position using[HS-85-5111], Rod Control Switch.[4]IF it is desired to leave[HS-85-5110], Rod Control Mode Selector in Manual for an extended period of time, THEN PLACE this Section in the Active Procedures
Book.[5]WHEN it is desired to place[HS-85-5110], Rod Control Mode Selector to Automatic, THEN GO TO Section 6.4.End of Section 6.5 1st CV 1st CV 1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 54 of 77 Unit Date----7.0 SHUTDOWN 7.1 Removing the MG Set A From Service[1]IF MG Set B has been removed from service, THEN[a]ENSURE the control rods and shutdown rods are fully inserted into the core.NOTE: The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional
Overcurrent
Relay contacts.[b]IF the reactor trip breakers are CLOSED THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons
[HS-3-99A]
and[HS-3-99B]
2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset Pushbuttons
[HS-3-99Al
and[HS-3-99B]
CAUTION Opening GENERATOR or MOTOR breaker of an MG Set that is to remain in service will result in a reactor trip.[2]OPEN MG Set A Load (GENERATOR)
Breaker 52-1 USING[HS-85-121.
D NOTE Voltage will be maintained
for a short time after opening the motor circuit breaker due to an intended time delay.[3]STOP CRD MG Set A by placing MOTOR Breaker 52A Circuit Control in the TRIP position USING[HS-85-1A].
[4]VERIFY MG Set A speed decreases.
End of Section 7.1 D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 55 of 77 Unit Date----7.2 Removing the MG Set B From Service[1]IF MG Set A has been removed from service, THEN[a]ENSURE the control rods and shutdown rods are fully inserted into the core.NOTE: The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional
Overcurrent
Relay contacts.[b]IF the reactor trip breakers are CLOSED THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons
[HS-3-99A]
and[HS-3-99Bl
2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset pushbuttons
[HS-3-99A]
and[HS-3-99Bl.
CAUTION Opening GENERATOR or MOTOR breaker of an MG Set that is to remain in service will result in a reactor trip.[2]OPEN MG Set B Load (GENERATOR)
Breaker 52-2 USING[HS-85-221.
D NOTE Voltage will be maintained
for a short time after opening the motor circuit breaker due to an intended time delay.[3]STOP CRD MG Set B by placing MOTOR Breaker 52B Circuit Control in the TRIP position USING[HS-85-1 B].[4]VERIFY MG Set B speed decreases.
End of Section 7.2 D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 56 of 77 Unit Date----8.0 INFREQUENT
OPERATION 8.1 Alternate Method of Paralleling
MG Set A CAUTION This method should only be used if one unit is on line and providing for a load that may cause too great a speed difference
to synchronize, and parallel operation is deemed necessary.
[1]OBTAIN Shift Manager's approval to perform this method of paralleling
MG Set A.//SM/SRO[2]ENSURE Section 6.1 has been completed.
[3]ENSURE CRDM MG Set A Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al
(67 A)[1-RL Y-085-DE/4D/Cl
(67C)[2-RLY-085-DG/4D/A]
(67A)[2-RL Y-085-DG/4D/Cl
(67C)[4]ENSURE targets for CRDM MG Set A Directional
Overcurrent
Relays are RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al
(67 A)[1-RLY-085-DE/4D/C]
(67C)[2-RL Y-085-DG/4D/A]
(67 A)[2-RL Y-085-DG/4D/Cl
(67C)[5]PLACE CRD MG Set A MOTOR Breaker 52A Circuit Control[HS-85-1Al
in the TRIP position.[6]VERIFY MG Set A speed decreases.
Date Time D D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 57 of 77 Unit Date----8.1 Alternate Method of Paralleling
MG Set A (Continued)
[7]IF MG Sets are paralleled, THEN[a]PLACE Gen No.1 SYNCHRONIZE
Switch[HS-85-12B]
in the OFF position.D[b]ENSURE target for CRD MG Set A Mtr Bkr 52A is RED by placing the MOTOR breaker circuit control[HS-85-1Al
in the CLOSE position.D[c]IF digital meters were used in Section 6.1, THEN A.ENSURE all digital meters are removed.__/__1st CV B.'ENSURE the MG Set panel doors are closed.1st CV[d]ENSURE target for CRD MG Set A Load (GENERATOR)
Bkr 52-1 is RED by placing the GENERATOR breaker circuit control in the CLOSE position.D[8]IF MG Set A does NOT parallel, THEN REPEAT Section 6.1 as required to synchronize
MG Sets.[9]CHECK all Power, Logic, and Hold cabinets for alarm lights.End of Section 8.1 D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 58 of 77 Unit Date_8.2 Alternate Method of Paralleling
MG Set B CAUTION This method should only be used if one unit is on line and providing for a load that may cause too great a speed difference
to synch, and parallel operation is deemed necessary.
[1]OBTAIN Shift Manager's approval to perform this method of paralleling
MG Set B.SM/SRO[2]ENSURE Section 6.2 has been completed.
[3]ENSURE CRDM MG Set B Directional
Overcurrent
Relay Target Coils are RESET (Panel(N/A other Unit)Relay INITIALS[1-RLY-085-DF/3B/A]
(67A)[1-RLY-085-DF/3B/C]
(67C)[2-RL Y-085-DH/3B/Al
(67 A)[2-RL Y-085-DH/3B/Cl
(67C)[4]ENSURE targets for CRDM MG Set B Directional
Overcurrent
Relays are RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al
(67 A)[1-RLY-085-DF/3B/C]
(67C)[2-RL Y-085-DH/3B/Al
(67 A)[2-RL Y-085-DH/3B/Cl
(67C)[5]PLACE CRD MG Set B MOTOR Breaker 528 Circuit Control[HS-85-1 B]in the TRIP position.[6]VERIFY MG Set 8 speed decreases.//Date Time D D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 59 of 77 Unit Date----8.2 Alternate Method of Paralleling
MG Set B (Continued)
[7]IF MG Sets are paralleled, THEN[a]PLACE[HS-85-22Bl
Gen NO.2 SYNCHRONIZE
Switch in the OFF position.[b]ENSURE target for CRD MG Set B Mtr Bkr 52B is RED by placing the MOTOR breaker circuit control[HS-85-1 B]in the CLOSE position.[c]IF digital meters were used in section 6.2, THEN 1.ENSURE all digital meters are removed.2.ENSURE the MG Set panel doors are closed.D D__I_-1st CV 1st CV[d]ENSURE target for CRD MG Set B Load (GENERATOR)
Bkr 52-2 is RED by placing the GENERATOR breaker circuit control in the CLOSE position.D[8]IF MG Set B does NOT parallel, THEN REPEAT Section 6.2 as required to synchronize
MG Sets.[9]CHECK all Power, Logic, and Hold cabinets for alarm lights.End of Section 8.2 D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 60 of 77 Unit Date_8.3 Resetting Step Counters After Withdrawing
Rods Above 231 StepsRamp Up ButtonStep Down ButtonReset to Zero LCD Step Counter[1]DEPRESS the affected group step counter"Step Down Button" to obtain 231 on display.[2]IF the affected bank is a control bank, THEN NOTIFY IMs to:[a]UPDATE the Pulse-to-Analog
converter.
[b]CHECK the bank overlap unit in the logic cabinet.[c]CHECK Master Cycler and UPDATE as needed.[3]ENSURE Plant computer points for rod bank position are UPDATED usingthefollowing
computer points: COMPUTER PT ROD BANKU0049 Control A D U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D UOO56 Shutdown D D End of Section 8.3 D D D
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 61 of 77 Unit Date----8.4 Resetting Step Counters After Inserting Rods Below 0 StepsRamp Up ButtonStep Down ButtonReset to Zero LCD Step Counter NOTE Depressing
the"Ramp Up Button" will cause a rapid change in the display.[1]MOMENTARILY
DEPRESS the affected group step counter"Ramp Up Button" to obtain 0 on display.[2]IF the affected bank is a control bank, THEN NOTIFY IMs to:[a]UPDATE the Pulse-to-Analog
converter.
D[b]CHECK the bank overlap unit in the logic cabinet.D[c]CHECK Master Cycler and UPDATE as needed.D[3]ENSURE Plant computer points for rod bank position are UPDATED using the following computer points: COMPUTER PT ROD BANKUOO49 Control A D U0050 Control B D UOO51 Control C D UOO52 Control D D UOO53 Shutdown A D UOO54 Shutdown B D UOO55 Shutdown C D U0056 Shutdown D D End of Section 8.4
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 62 of 77 Unit Date----8.5 Placing MG Set A In Service for Maintenance
[1]ENSURE clearance in place to isolate power to Rod Control coils on reactor head AND RECORD Hold Order Number.------[2]START CRD MG Set A by placing[HS-85-1Al
MOTOR Breaker 52A Circuit Control in the CLOSE position.NOTE Allow 15 seconds for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.
[4]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.
[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.
[5]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts.NOTE Voltage may vary slightly between phases.[6]CHECK voltage approximately
equal on all phases using voltmeter selector switch.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 63 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenance(Continued)
[7]WHEN Maintenance
requires MG Set A Load Breaker to be closed, THEN PERFORM the following:
NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[a]ENSURE MG Set A Load (GENERATOR)
Breaker 52-1[BCTF-85-121
is RACKED IN.[b]ENSURE MG Set B Load (GENERATOR)
Breaker 52-2[BCTF-85-221
is RACKED IN.[c]ENSURE CRDM MG Set A Directional
Overcurrent
Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]
(67 A)[1-RLY-085-DE/4D/Cl
(67C)[2-RL Y-085-DG/4D/Al
(67 A)[2-RL Y-085-DG/4D/Cl
(67C)[d]ENSURE targets for CRDM MG Set A
Overcurrent
Relays are RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4DI
Al (67 A)[1-RL Y-085-DE/4D/C]
(67C)[2-RLY-085-DG/4D/Al
(67 A)[2-RL Y-085-DG/4D/Cl
(67C)
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 64 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenanee(Continued)
NOTE Generator voltage will drop slightly as the electrical
load increases.
[e]CLOSE MG Set A Load (GENERATOR)
Breaker 52-1 USING[HS-85-12].
[f]IF MG Set A Load breaker 52-1 trips due to Directional
Overcurrent
Relay operation, THEN[1]RESET Directional
Overcurrent
Relays with Relay Target Reset Button on Relay panel.[2]RESET Directional
Overcurrent
Relay Targets.[3]RECLOSE MG Set A load Breaker 52-1 USING[HS-85-12].
[4]IF another trip of breaker 52-1 occurs, THEN REPEAT substeps[a],[b]and[e].[5]IF breaker 52-1 trips the third time, THEN NOTIFY SM and System Engineering
for assistance.
[8]WHEN MAINTENANCE
requires reactor trip/bypass
breakers to be closed, THEN PERFORM the following:
[a]ENSURE[1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED.(located in Panel L-115).[b]ENSURE lift coil disconnect
switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 65 of 77 Unit Date_8.5 Plac-ing MG Set A In Service for Maintenance(Continued)
CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[c]MOMENTARILY
PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY group step counters are at zero steps.[d]ENSURE Reactor Trip Bypass breakers are in required alignment per Maintenance
Procedure:
BYPASS RACKED IN RACKED OUT BREAKERBYA D D BYB D D[e]ENSURE Reactor Trip breakers are in required alignment per Maintenance
Procedure:
TRIP RACKED IN RACKED OUT BREAKERRTA D D RTB D D[f]ENSURE control power is ON by GREEN indicating
lights on M-4: (NA breakers not racked in)BREAKER GREEN INITIALS LIGHT RTA ON RTB ON BYA ON BYB ON
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 66 of 77 Unit Date----8.5 Placing MG Set A In Service for Maintenance(Continued)
[g]ENSURE Rod Control switch[HS-85-5111]
is in MID position.[h]IF unit is in Mode 3,THEN ENSURE requirements
of Tech Spec 3.4.1.2 are met.[i]DEPRESS and HOLD FW Isol Reset push buttons[HS-3-99Al
and[HS-3-99Bl.[C.1]
U]IF maintenance
being performed on Unit 1, THEN CLOSE Rx Trip Breakers by placing[1-RT-11, to CLOSE position.[k]IF maintenance
being performed on Unit 2, THEN CLOSE Rx Trip Breakers by placing[2-HS-99-7], to CLOSE position.[I]VERIFY Reactor Trip Breakers/Reactor
Trip Bypass breakers CLOSED by RED indicating
lights on M-4: (NA breakers not closed)BREAKER RED LIGHT INITIALS RTA ON RTB ON BYA ON BYB ON[m]RELEASE FW Isol Reset pushbuttons
[HS-3-99Al
and[HS-3-99B].[C.1]
[n]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 67 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenance(Continued)
[9]WHEN desired to shutdown MG Set A, THEN PERFORM the following:
NOTE The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional
Overcurrent
Relay contacts.[a]IF the reactor trip breakers are CLOSED, THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons
[HS-3-99Al
and[HS-3-99B].
2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset Pushbuttons
[HS-3-99Al
and
[b]OPEN MG Set A Load (GENERATOR)
Breaker 52-1 USING[HS-85-12].
NOTE Voltage will be maintained
for a short time after opening the motor circuit breaker due to an intended time delay.[c]STOP CRD MG Set A by placing MOTOR Breaker 52A Circuit Control in the TRIP position USING[HS-85-1A].
[d]VERIFY MG Set A speed decreases.
SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 68 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenance(Continued)
NOTE The following step maybe NA if returned to normal by the clearance process.[10]WHEN maintenance
complete, AND Reactor Trip and Bypass breakers ready to return to normal, THEN PERFORM the following:
[a]ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT.BYPASS OPENRACKED OUT BREAKERBYA D D BYB D D[b]ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKERRTA D RTB D[c]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts.End of Section 8.5
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 69 of 77 Date----Placing MG Set B In Service for Maintenance
Unit------8.6[1]ENSURE clearance in place to isolate power to Rod Control coils on reactor head AND RECORD Hold Order Number.[2]START CRD MG Set 8 by placing[HS-85-1 B]MOTOR Breaker 528 Circuit Control in the CLOSE position.D NOTE Allow 15
for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.
[4]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.
[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.
[5]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts.NOTE Voltage may vary slightly between phases.[6]CHECK voltage approximately
equal on all phases using voltmeter selector switch.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 70 of 77 Date----Placing MG Set B In Service for Maintenance
Unit------8.6[7]WHEN Maintenance
requires MG Set B Load Breaker to be closed THEN PERFORM the following:
NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[a]ENSURE MG Set A Load (GENERATOR)
Breaker 52-1[BCTF-85-12l
is RACKED IN.[b]ENSURE MG Set B Load (GENERATOR)
Breaker 52-2[BCTF-85-22l
is RACKED IN.[c]ENSURE CRDM MG Set B Directional
Overcurrent
Relay Target Coils for are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/A]
(67 A)[1-RLY-085-DF/3B/C]
(67C)[2-RLY-085-DH/3B/Al
(67A)[2-RL Y-085-DH/3B/C]
(67C)[d]ENSURE targets for CRDM MG Set B Directional
Overcurrent
Relays are RESET (Mechanical
Linkage on relay).(N/A other Unit)Relay INITIALS[1-RLY-085-DF/3B/A]
(67A)[1-RL Y-085-DF/3B/Cl
(67C)[2-RLY-085-DH/3B/A]
(67A)[2-RL Y-085-DH/3B/Cl
(67C)
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 71 of 77 Date_Placing MG SetB In Service for Maintenance
Unit------8.6 NOTE Generator voltage will drop slightly as the electrical
load increases.
[e]CLOSE MG Set B Load (GENERATOR)
Breaker 52-2 USING[HS-85-22].
IF another trip of breaker 52-2 occurs, THEN REPEAT substeps[a],[b]and[c].IF breaker 52-2 trips the third time, THEN NOTIFY SM and System Engineering
for assistance.
[5][f]IF MG Set B Load breaker 52-2 trips due to Directional
Overcurrent
Relay operation, THEN[1]RESET Directional
Overcurrent
Relays with Relay Target Reset Button on Relay panel.[2]RESET Directional
Overcurrent
Relay Targets.[3]RECLOSE MG Set A load Breaker 52-2.[4][8]WHEN MAINTENANCE
requiresreactortrip/bypass
breakers to be closed, THEN PERFORM the following:
[a]ENSURE[1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED.(located in Panel L-115).[b]ENSURE lift coil disconnect
switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 72 of 77 Date----Placing MG Set B In Service for Maintenance
Unit------8.6 CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[c]MOMENTARILY
PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY group step counters are at zero steps.[d]ENSURE Reactor Trip Bypass breakers are in required alignment per maintenance
procedure.
BYPASS RACKED IN RACKED OUT BREAKERBYA D D BYB D D[e]ENSURE Reactor Trip breakers are in required alignment.t d per main enance proce ure.TRIP RACKED IN RACKED OUT BREAKERRTA D D RTB D D Cco,[f]ENSURE control power is ON by GREEN indicating
lights on M-4: (NA breakers not racked in)BREAKER GREEN INITIALS LIGHT RTA ON RTB ON BYA ON BYB ON[g]ENSURE Rod Control switch[HS-85-51111
is in MID position.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 73 of 77 Unit Date_8.6 Placing MG Set B In Service for Maintenance
[h]IF unit is in Mode 3,THEN ENSURE requirements
of Tech Spec 3.4.1.2 are met.[i]DEPRESS and HOLD FW Isol Reset pushbuttons
[HS-3-99Al
and[HS-3-99Bl.[C.1]
[j]IF maintenance
being performed on Unit 1, THEN CLOSE Rx Trip Breakers by placing[1-RT-1], to CLOSE position.[k]IF maintenance
being performed on Unit 2, THEN CLOSE Rx Trip Breakers by placing[2-HS-99-7], to CLOSE position.[I]VERIFY Reactor Trip Breakers/Reactor
Trip Bypass breakers CLOSED by RED indicating
lights on M-4: (NA breakers not closed)BREAKER RED LIGHT INITIALS RTA ON RTB ON BYA ON BYB ON[m]RELEASE FW Isol Reset pushbuttons
[HS-3-99A]
and[HS-3-99B].[C.1]
[n]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 74 of 77 Unit Date_8.6 Placing MG Set B In Service for Maintenance
[9]NOTE WHEN desired to shutdown MG Set B, THEN PERFORM the following:
The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional
Overcurrent
Relay contacts.[a]IF the reactor trip breakers are CLOSED, THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons
[HS-3-99A]
and[HS-3-99B]
2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset Pushbuttons
[HS-3-99Al
and[HS-3-99Bl
[b]OPEN MG Set B Load (GENERATOR)
Breaker 52-2 USING[HS-85-22].
NOTE Voltage will be maintained
for a short time after opening the motor circuit breaker due to an intended time delay.[c]STOP CRD MG Set B by placing MOTOR Breaker 52B Circuit Control in the TRIP position.USING[HS-85-1B].
[d]VERIFY MG Set B speed decreases.
SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 75 of 77 Unit Date----8.6 Placing MG Set B In Service for Maintenance
NOTE The following stepmaybeNA if returned to normal by the clearance process.[10]WHEN maintenance
complete AND Reactor Trip and Bypass breakers ready to return to normal, THEN PERFORM the following:
[a]ENSURE Reactor Trip Bypass breakers BY A and BYB are OPEN and RACKED OUT.BYPASS OPEN (-V)RACKED OUT BREAKERBYA D D BYB D D[b]ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKERRTA D RTB D[c]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification
of P4 Contacts.End of Section 8.6
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 76 of 77 9.0 RECORDS A.Completed copies of sections shall be transmitted
to the Operations
Superintendent's
Secretary.
SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 77 of 77 SOURCE NOTES Page 1 of 1 IMPLEMENTING
STATEMENT[C.1][C.2]REQUIREMENTS
DOCUMENT NC00940183003
8Q94026311
LER327/94005
LER328/94008
REQUIREMENTS
STATEMENT Revised procedure to require feedwater isolation reset buttons to be held during closure of reactor trip breakers.Revised procedure to operate the thrust switch in a more conservative
method to minimize the possibility
of step deviations
greater than two steps during initial rod movement.
0.
JPM B.1.d Page 10f 9 Rev.0 SEQUOYAH NUCLEAR PLANT JOB PERFORM*ANCE
MEASURE B.1.d JPM FILLI'NG AND VENTING EXCESS LETDOWN PREPAREDI REVISED BY: VALIDATED BY:*APPROVED BY: (Operations
Training Manager)Date/Date/Date/CONCURRED:
**(Operations
Representative)
Date/*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual
step changes that do not affect the flow of the JPM.**Operations
Concurrence
required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM B.1.d Page 2 of 9 Rev.0 I NUCLEAR TRAINING REVISION/USAGE
LOG REVISION DESCRIPTION
OF V DATE PAGES PREPAREDI NUMBER REVISION AFFECTED REVISED BY: 0 New Y Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.
JPM B.1.d Page 3 of 9 Rev.0 SEQUOYAH NUCLEAR PLANT RO/SRO JOBPERFORMANCEMEASURE
Task: Filling and Venting Excess Letdown JAITA task:#0040160101 (RO)Place Excess Letdown in Service KIA Ratings: 004 Chemical And Volume Control System A4 Ability to manually operate and/or monitor in the control room (CFR 41.7/45.5 to 45.8)A4.06 Letdown isolation and flow control valves 3.6/3.1 Task Standard: 1)Excess letdown is filled and vented in accordance
with 1-S0-62-6, Excess Letdown, section 8.1 Evaluation
Method: Simulator__X_In-Plant_===================================================================================
Performer:
Performance
Rating: SAT Evaluator:
NAME UNSAT SIGNATURE Performance
Time DATE Start Time_Finish Time_==============.=====================================================================
COMMENTS
JPM B.1.d Page 4 of 9 Rev.0 SPECIAL INSTRUCTIONS
TO EVALUATOR:
1.Sequenced steps identified
by an"s" 2.Any UNSAT requires comments 3.This task is to be performed using the simulator in Ie 6.4.Ensure operator performs the following required actions for SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.9 min Local-----Tools/Equipment/Procedures
Needed: 1-S0-62-6 References:
1.1-S0-62-6 Excess Letdown Title Rev16=.============================================================================
READ TO OPERATOR Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job*performance
measure will be satisfied.
Ensure you indicate.tome when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.Plant is in Mode 3.2.Excess letdown system has been out of service for maintenance.
3.The work is complete and the system is ready to be filled and vented.2.You are an extra RO on shift INITIATING
CUES: 1.The SRO has directed you to fill and vent Excess Letdown.2.You are to notify the SRO when you have completed filling and venting Excess Letdown in accordance
with1-S0-62-6, Excess Letdown.3.Section 4, Prerequisites
Actions, has been completed.
Job Performance
Checklist STEP/ST ANDARD JPM B.1.d Page 50f9 Rev.0 SAT/UNSAT STEP 1.: Obtain the appropriate
procedure.
-SAT-UNSAT STANDARD: Operator identifies
1-S0-62-6 and goes to section 8.1"Filling and Venting Excess Letdown".Start Time--COMMENTS: STEP 2.: NOTE An AUO at panel O-L-2 will be needed to observe an increase in the-SAT RCDT level.-UNSAT Cue: When AUO is directed to O-L-2, Acknowledge
the direction STANDARD: An AUO is directed to be stationed at panel O-L-2 to observe RCDT level.COMMENTS: STEP 3.:[1]ENSURE
CCS water to Excess Letdown Heat Exchanger is-SAT OPEN.-UNSAT STANDARD: Candidate determines
l-FCV-70-143
is open by the red light lit above 1- EXCESS LETDOWN HX INLET ISOL, on O-M-278.COMMENTS: STEP 4.:[2]OPEN[1-FCV-70-85]
Excess Letdown Heat Exchanger CCS Flow Control.-SAT-UNSAT STANDARD: Candidate places 1-HS-70-85A, EXCESS LETDOWN HX OUTLET ISOL, to the OPEN position on O-M-278 and Holds until the valve is full open (red light is lit and the green light light is dark.)Criti.cal Step COMMENTS:
Job Performance
Checklist STEP/ST ANDARD JPM B.1.d Page 6 of 9 Rev.0 SAT/UNSAT STEP 5.:[3]PLACE[1-FCV-62-59]
Excess Letdown 3-way Divert Valve in DIVERT.-SAT-UNSAT STANDARD: Candidate places 1-HS-62-59, EXCESS LTDN DIVERT, to the DIVERT position on 1-M-5.Right side red light will be lit, left side red light will be dark.Critical.Step COMMENTS: STEP 6.:[4]OPEN[1-FCV-62-54]
Cold Leg Loop#3 Excess Letdown Isolation Valve.-SAT-UNSAT STANDARD: Candidate places 1-HS-62-54A, Excess Letdown Isolation, to the OPEN position on 1-M-5.Red light above handswitch
will be lit.Critical COMMENTS: Step STEP 7.:[5]OPEN[1-FCV-62-55]
Excess Letdown Containment
Isolation Valve.-SAT-UNSAT STANDARD: Candidate places 1-HS-62-55A, Excess Letdown Isolation, to the OPEN position on 1-M-5.Red light above handswitch
will be lit.Critical Step COMMENTS:
Job Performance
Checklist STEP/ST ANDARD JPM B.1.d Page 7 of 9 Rev.0 SAT/UNSAT STEP 8.:[6]OPEN[1-FCV-62-S6]
Excess Letdown Flow Control Valve.-SAT Note: The procedure contains this note prior to the step-UNSAT"NOTE At the completion
of step[6]a timed duration will be initiated." Cue: After the FCV is opened, state that 5 minutes has elapsed.Critical Step STANDARD: Candidates
rotates handswitch
1-HIC-62-56, Excess L TDN Flow Control Valve, to the counter-clockwise
to greater than the'0" position on 1-M-5.Evaluator Note: Temperature
and pressure rise will be indicated on 1-TI-62-58 and 1-PI-62-57 respectively
Cue: If Excess Letdown Hx Temp alarm comes in, state that the temperature
is high but has stabilized.
COMMENTS: STEP 9.:[7]OBSERVE level increase in RCDT for 5 minutes-SAT-UNSAT Cue: When AUO contacted, state"The RCDT level has been continuously
increasing
for the last 5 minutes-" STANDARD: AUO is contacted to monitor RCDT level.(RDCT level can also be monitored on the ICS)COMMENTS: STEP 10.: 8]WHEN 5 minutes haselapsed,THEN
CLOSE[1-FCV-62-S6]
Excess-SAT Letdown Flow Control Valve.-UNSAT STANDARD: Candidates
rotates handswitch
1-HIC-62-56, Excess L TDN Flow Control Valve, on 1-M-5, clockwise to the'0" position.Critical Step COMMENTS:
Job Performance
Checklist STEP/STANDARD
STEP 11.:[9]CLOSE the following valves: JPM B.1.d Page 8 of 9 Rev.0 SAT/UNSAT SAT VALVE UlENTIFICA
TIO:N lNITIAlS UNSAT l-FCV-62-55
Ex.;cl:.s.s
Letdklvm Conlainrnent
Isolaticn l-FCV-02...Et4.C,old Leg Loc:p#3
Letdown
l-FCV-7"G'-B5
Ex:C*ss LetdCfim Heat Exchang?ef" CCS FCV Critical Step Cue: If IV is requested, state"An individual
will be assigned to performed the IV" STANDARD: Candidate closes the the listed valves by placing the respective
handswitches
(1-HS-62-55
&1-HS-62-54
on 1-M-5, and 1-HS-70-85
onM-27B)to the CLOSE position.Red light will go dark and green light will be lit.COMMENTS: STEP 12.:[10]PLACE[1-FCV-62-59]
Excess Letdown 3-way Divert Valve in NORMAL.STANDARD: Candidate places 1-HS-62-59, EXCESS L TDN DIVERT, on 1-M-5 to the NORMAL position.Right side red light will be dark, left side red light will be lit.COMMENTS: STEP 13.: Notifcation
of completion
of 1-S0-62-7 is made to the SRO.STANDARD: SRO is notified that Excess Letdown is filled and vented.COMMENTS: End of JPM SAT UNSAT Critical Step SAT UNSAT Stop Time__
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION
OF TASK)DIRECTION TO TRAINEE:'I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating
cues and reports on other actions when directed by you.Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.IN.ITIAL CONDITIONS:
1.Plant is in Mode2.Excess letdown system has been out of service for maintenance.
3.The work is complete and the system is ready to be filled and vented.2.You are an extra RO on shift.INITIATING
CUES: 1.The SRO has directed you to fill and vent Excess Letdown.2.You are to notify the SROwhen YO'u have completed filling and venting Excess Letdown in accordance
with 1-S0-62-6, Excess Letdown.3.Section 4, Prerequisites
Actions, has been completed.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION
1-50-62-6" EXCESS LETDOWN Revision 16 QUALITY RELATED MS LEENERTS OPERATIONS
RESPONSIBLE
ORGANIZATION:
---------------
w.T.LEARY APPROVED BY:
EFFECTIVE DATE: 06/05/07 LEVEL OF USE: CONTINUOUS
USE REVISION DESCRIPTION:
Revised Attachment
2 to change position of 1-70-702C from CLOSED&CAPPED to LOCKED CLOSED&CAPPED and changed verification
from IV to CV (NB070420).
THIS PROCEDURE COULD AFFECT REACTIVITY
SQN EXCESS LETDOWN 1-S0-62-6Rev:16 1 Page 2 of 14 TABLE OF CONTENTS Page 1 of 1 Section Title Page 1.0 INTRODUCTION
3 1.1 Purpose*.................................................................................................................
3 1.2 Scope 3 2.0 REFERENCES
3 2.1 Performance*
References.....
3 2.2 Developmental
References....................................
3 3.0 PRECAUTIONS
AND LIMITATIONS
4 4.0 PREREQUISITE
ACTIONS 5 5.0 STARTUP/STANDBY
READINESS 6 6.0 N*ORMAL OPERATION 9 7.0 SHUTDOWN 10 8.0 INFREQUENT
OPERATION 12 8.1 Filling and Venting Excess Letdown 12 9.0 RECORDS 14 ATTACHMENTS
ATTACHMENT
1: POWER CHECKLIST 1-62-6.01 ATIACHMENT
2: VALVE CHECKLIST 1-62-6.02
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 30f 14 1.0 INTRODUCTION
1.1 Purpose To provide instructions
for the operation of excess letdown.1.2 Scope A.Placing excess letdown in service.B.Ta-king excess letdown out of service.2.0 REFERENCES
2.1 Performance
References
None.2.2 Developmental
References
A.801-62.1, Chemical and Volume Control System B.1-80-62-1, Chemical and Volume Control System C.TVA Drawings 1.47W809-1 2.47W859-2 D.SQN-VTM-1201-0010
Grinnell Valve vendor manual
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 4 of 14 3.0 PRECAUTIONS
AND LIMITATIONS
A.Failureto observe all posted radiation control requirements
may lead to unnecessary
radiation absorbed doses.B.When placing Excess Letdown in service to replace normal letdown, the charging flow temperature
may cool enough to lower the ReS average temperature
and may cause a change in reactivity.
C.The fluid outlet temperature
of the excess letdown heat exchanger-should
not exceed 200&deg;F.The maximum allowable temperature
is 250&deg;F.D.While placing the excess letdown heat exchanger in service the Rep seal leakoff flow may fluctuate, therefore periodic monitoring
should be maintained.
E.When Excess Letdown is placed in service an approximate
increase of 100 CPM maybe observed on 1-RM-90-106A.
This elevated radiation monitor reading should start to trend back to normal after approximately
one hour.F.Operation of Excess Letdown with 1-TI-62-58 (Excess Letdn Temp)greater than 200&deg;F will require that Systems Engineering
be notified so that an evaluation
of Grinnell valve maintenance
can be conducted.
SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 5 of 14 Date-------4.0 PREREQUISITE
ACTIONS NOTE Throughout
this Instruction, where an IFITHEN statement exists, the step should be N/A if condition does not exist.[1]ENSURE Instruction
to be used is a copy of effective version.[2]VERIFY CVCS system is in service in accordance
with Valve Checklists
1-62-1.03 and 1-62-1.04.
[3]ENSURE Attachment
1, Power Checklist 1-62-6.01 has been completed.
[4]ENSURE Attachment
2, Valve Checklist 1-62-6.02 has been completed.
[5]ENSURE Precautions
and Limitations, Section 3.0 have been reviewed.[6]ENSURE each performer documents their name and initials:/""\Print Name Initials I
b/'t:>oK,5
;;)-[7]INDICATE below which performance
section of this instruction
will be used and the reason for this performance:
o 5.0 STARTUP/STANDBY
READ.INESS
REASON: INFREQUENT
OPERATION c7 I o 7.0 SHUTDOWN W 8.0
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 6of14 Date----5.0 STARTUP/STANDBY
READINESS NOTE 1 NOTE 2 When excess letdown is placed in service the containment
radiation monitors may show some changes in particulate
reading.Coordinate
the following steps with AUO stationed at O-L-2 to monitor RCDT for pump operation as required during the 50 gallon flush.[1]ENSURE[1-FCV-62-931
is in MANUAL and[a]OPERATE[1-FCV-62-931
USING[1-HIC-62-93A]
as required to regulate charging flow to keep pressurizer
level,on program.[b]OPERATE[1-FCV-62-89]
USING[1-HIC-62-89A]
as required to maintain Rep seal flows in limits.[2]NOTIFY RADCON that Excess Letdown is being placed in service.[3]ENSURE[1-FCV-70-1431
CCS water to the excess letdown heat exchanger is OPEN.[4]ENSURE[1-FCV-70-851
Excess Letdown Heat Exchanger CCS flow control valve is OPEN.NOTE Step[5]will prevent subjecting
the cves piping downstream
of the Excess Letdown HX to a temperature
above the design value.[5]ENSURE[1-FI-70-841
is indicating
greater than 230 gpm.[6]PLACE[1.-FCV-62-591
Excess Letdown 3-way Divert Valve in DIVERT.
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 7 of 14 Date----5.0 STARTUP/STANDBYREADINESS(Continued)
CAUTION NOTE FCV 62-63 has replaced RCP seal leak-off isolation valves as the primary means for isolating seal flow.The normal letdown path for excess letdown will not be available if FCV-62-63 is CLOSED.Back flow through the RCP seals will occur should the RCP seal leakoff isolation valves fail to their OPEN position on loss of air or electrical
p.ower.[7]IF less than 100 psig in RCS and[1-FCV-62-63l
is CL*OSED and excess letdown will be aligned for NORMAL operation, THEN[a]ENSURE the following are CLOSED: VALVEID FUNCTION INITIALS 1-FCV-62-53
RCP's Seal Bypass 1-FCV-62-9
No.1 Seal Return 1-FCV-62-22
NO.2 Seal Return 1-FCV-62-35
NO.3 Seal Return 1-FCV-62-48
NO.4 Seal Return[b]ENSURE[1-FCV-62-63]is
OPEN.[8]OPEN[1-FCV-62-54]
Cold Leg Loop#3 Excess Letdown isolation valve.[9]OPEN
Excess Letdown containment
isolation valve.
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 8 of 14 Date----5.0 STARTUP/STANDBY
READINESS(Continued)
NOTE ICS point 1 L2400A or the AUO stationed at 0-L-2 can be used to monitor RCDT for level increase during the 50 gallon flush.Reference the RCDT Level vs Volume table in TI-28.[10]OPEN[1-FCV-62-561
slowly to flush piping to RCDT.[11]WHEN approximately
50 gallons have flushed, THEN CLOSE[1-FCV-62-56], Excess Letdown Flow Control Valve.1st IV[12]PLACE[1-FCV-62-59]
Excess Letdown 3-way Divert Valve in NORMAL.1st IV NOTE 1 NOTE 2 Normally the temperature
read on 1-TI-62-58
should be less than 200&deg;F.If operation requires temperatures
greater than 200&deg;F, the pressure at 1-PI-62-64 (local indicator EI.690 Pnl L-46)should be less than 100 psig to protect the Grinnell valves.Operation above 200&deg;F will require that Systems Engineering
be notified to allow an evaluation
of the need for valve maintenance.
[13]OPEN[1-FCV-62-561
slowly to increase excess letdown flow to desired amount, not to exceed 240&deg;F heat e*xchanger
outlet temperature, as indicated on 1-TI-62-58.
NOTE Placing Excess Letdown in service causes increased activity in various areas of the Auxiliary Building.[14]NOTIFY RADCON thatExcess
Letdown has been placed in service.END OF TEXT
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 9 of 14 6.0 NORMAL OPERATION None.
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 10 of 14 Date 7.0 SHUTDOWN[1]IF letdown is to be placed in service, THEN RETURN to service per 1-S0-62-1.
[2]C*LOSE[1-FCV-62-56]
Excess Letd.own Heat Exchanger outlet valve.1 st IV[3]VERIFY[1-FCV-62-59]Excess Letdown 3-way valve in NORMAL.1 st IV[4]CLOSE[1-FCV-62-55]
Excess Letdown containment
isolation valve.1 st IV[5]CLOSE[1-FCV-62-54]
Cold Leg Loop#3 Excess Letdown valve.1st IV[6]IF charging is in service, THEN ADJUST seal injection flow to 6-11gpm using[1-FCV-62-89].
[7]IF auto operation is desired and system conditions
will allow it, THEN PLACE[1-FCV-62-93]
in AUTO.[8]NOTIFY RADCON that Excess Letdown is REMOVED from SERVICE.
SQN EXCES5LETDOWN
1-50-62-6Rev:16 1 Page 11 of 14 Date_7.0 SHUTDOWN[9]ENSURE[1-FCV-70-851
Excess Letdown HX CCS Flow Control Valve is CLOSED.[10]ENSURE[1-HS-70-85Al
is in the A-AUTO position.[11]IF operation at greater than 200 of has occurred, THEN CONTACT Systems Engineering
to evaluate Grinnell valve maintenance
requirements.
E*ND OF TEXT 1st 1 st IV IV
SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 12 of 14 Date----8.0" INFREQUENT
OPERATION 8.1 Filling and Venting Excess Letdown NOTE An AUG at panel O-L-2 will be needed to observe an increase in the RCDT level.[1]ENSURE[1-FCV-70-1431
CCS water to Excess Letdown Heat Exchanger is OPEN.[2]OPEN[1-FCV-70-85l
Excess Letdown Heat Exchanger CCS Flow Control.[3]PLACE[1-F"CV-62-59]
Excess Letdown 3-way Divert Valve in DIVERT.[4]OPEN
Cold LegLoop#3 Excess Letdown Isolation Valve.[5]OPEN[1-FCV-62-55]
Excess Letdown Containment
Isolation Valve.NOTE At the completion
of step[6]a timed duration will be initiated.
[6]OPEN[1-FCV-62-56]
Excess Letdown Flow Control Valve.[7]OBSERVE level increase in RCDT for 5 minutes.[8]WHEN 5 minutes has elapsed, THEN CLOSE[1-FCV-62-561
Excess Letdown Flow Control Valve.1 st IV
SQN EXCESS LETDOWN 1-S0-62-6Rev:16 1 Page 13 of 14 Date-------8.1 Filling and Venting Excess Letdown (Continued)
[9]CLOSE the following valves: VALVE IDENTIFICATION
INITIALS 1-FCV-62-55
Excess Letdown Containment
Isolation-1-st-IV 1
Cold Leg Loop#3 Excess Letdown Isolation-1-st-IV 1-FCV-70-85
Excess Letdown Heat'Exchanger
CCS FCV-1-st-IV[10]PLACE[1-FCV-62-59]Excess Letdown 3-way Divert Valve in NORMAL.END OF TEXT 1 st IV
SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 14 of 14 9.0 RECORDS Completed copies of all Sections shall be transmitted
to the Operations
Superintendents
Secretary.
u.S c....l S;a CD
PREPAREDI REVISED BY: JPM#75AP Page 1 of 10 Rev.8 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE
MEASURE B.1.e JPM#75-AP SteamGeneratorTube
Rupture (With MSIV Failure to Close)Date/VALIDATED BY:*APPROVED BY: Date/Date!(Operations
Training Manager)CONCURRED:
**Date/(Operations
Representative)
*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual
step changes that do not affect the flow of the JPM.**Operations
Concurrence
required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM#75AP Page 2 of 10 Rev.8 r NUCLEAR TRAINING REVISION/USAGE
LOG REVISION DESCRIPTION
OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 3 Transfer from WP.Minor enhancements.
N 10/15/94 All HJ Birch 4 Incorporate
Rev B changes.Changed to Y 9/16/95 All HJ Birch S/G#1 to force swap of TDAFW steam supply.pen/ink Added closed, to verify Atm Relief vlvs in N 12/7/95 5,6 HJ Birch auto.Also enhance standard for MSIV bypasses nota JPM critical task.E-O Rev chg only.N 2/6/97 4 HJ Birch pen/ink revision had no impact N 8/11/98 All JP Kearney pen/ink E-O Rev chg only.N 9/23/99 4 SR Taylor pen/ink E-O Rev 22 chg only.E-3 Rev 12 minor N 09/05/01 ALL WR Ramsey changes 5 Incorporated
pen/ink changes N 8/22/02 AllJP Kearney 6 Updated to current revision and IC.N 8/10/04 All MG Croteau 7 Updated references
and reordered steps N 10/28/200 ALL JJ Tricoglou to conform to the latest revision to E-3.5 Deleted Critical Step 9 as this*step was deleted from the procedure 8 Update to E-3 rev 17, added candidate N All handout sheet, modified instructions
and steps to reflect instruction
revision and provide clarity.v-Specify if the JPM change will require another validation (Yor N).See cover sheet for criteria.
JPM#75AP Page 3 of 10 Rev.8 SEQUOY AH NUCLEAR PLANT RO/SRO JOB PERFORMANCE
MEASURE Task: Steam Generator Tube Rupture (With MSIV Failure to Close)JAlTA task#: 0000380501 (RO)KIA Ratings: 038EA1.32 (4.6-4.7)Task Standard: Steam Generator#1 isolated per E-3.Evaluation
Method: Simulator__X__In-Plant_====================================================================================
Performer:*
Performance
Rating: SAT Evaluator:
NAME UNSAT SIGNATURE Performance
Time DATE Start Time__-,--Finish Time_====================================================================================
COMMENTS
JPM#75AP Page 4 of 10 Rev.8 SPECIAL INSTRUCTIONS
TO EVALUATOR:
1.Sequenced steps identified
by an"s" 2.AnyUNSAT requires comments 3.Initialize
simulator in IC#175.4.If snapshot unavailable, then Initialize
simulator in IC#16 and Insert the following:
a.Activate malfunction
IMF TH05A f:8.5 to initiate S/G tube rupture in S/G#1.b.Activate malfunction
IMF MS14A f:100, to fail open S/G Loop 1 MSIV.c.Complete the actions of E-O thru step 12, which will transition
the crews to E-3 d.Complete any required actions in ES-0.5.Including closing the TD AFW LCVs, but do not put handswitches
in pull-to-Iock.
e.Complete the first three ste.ps in E-3.f.Actuate a MANUAL reactor trip and safety injection, take all actions up through Step 3 of E-3.5.Freeze the simulator until the operator is ready to begin the JPM.6.Ensure operator performs the following required actions for SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.12 mins Local_Tools/Equipment/Procedures
Needed: E-3 References:
Rev No.A.E-O Reactor Trip or Safety Injection 29 B.E8-0.5 Equipment Verifications
0 C.E-3 Steam Generator Tube Rupture 17=======================================================
Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
Unit 1 has experienced
a SGTR.A manual safety injection was initiated and E-O implemented.
E-O and E.S-0.5 have been completed and a transition
to E-3 has been made.Steps 1 through 3 of E-3 have been completed and S/G#1 has been identified
as the ruptured S/G.INITIATING
CUES: You are the eRO and are directed to continue with the actions/responses
of 6-3, beginning at Step 4.Inform the SRO when you are ready to determine the Target Core Exit Thermocouple
temperature.
Job Performance
Checklist:
STEP/STANDARD
JPM#75AP Page 5 of 10 SAT/UNSAT STEP 1.: Obtain appropriate
copy of procedure.
-SAT STANDARD: Operator obtains a copy of E-3 andcontinuesat
step 4 as directed.-UNSAT COMMENTS: Start Time--STEP 2.:[4.a]ADJUST Ruptured S/Gs atmospheric
relief controller
setpoint to-SAT 87%in AUTO.(1040 psig)-UNSAT STANDARD: Operator adj.usts PIC-1-6A to 87%and ensures the controller
is in auto.Critical Step COMMENTS: SToEP 3.:[4.b]CHECK Ruptured S/G atmospheric
relief handswitch
in P-AUTO-SAT and CLOSED.-UNSAT STANDARD: Operator checks S/G#1 atmospheric
relief HS, FCV-1-6, on 1-M-4in P-AUTO and checks green light LIT abovehandswitch.
COMMENTS: STEP 4:[4.c]CLOSE TD AFW pump steam supply from Ruptured S/G FCV-1--SAT 15 (S/G#1)or FCV-1-16 (SIG#4).-UNSAT STANDARD: Operator closes FCV-1-15 and verifies closed by GREEN light LIT ON 1-M-4[Critical part of step].May verify that FCV-1-16, S/G#4, auto opens or may open valve manually, approx 1 minute later, with red light Critical Step LIT, not critical).
COMMENTS: STEP 4.:[4.d]VERIFY RupturedS/G
blowdown isolation valves Closed.-SAT STANDARD: Operator verifies FCV-1-7 and
CLOSED as indicated by-UNSAT green indication
lights above handswitch
1-HS-1-7/181
on 1-M-4.COMMENTS:
Job Performance
Checklist:
STEP/ST ANDARD JPM#75AP Page 6 of 10 SAT/UNSAT STEP 5.:[4.e]CLOSE Ruptured S/G MSIV and MSIV Bypass Valve.-SAT Note: SIG#1 MSIV will NOT close and the operator MUST go to theRNO-UNSAT column at this time.STANDARD: Attempts to close MSIV FSV-1-4.Recognizes
the MSIV failed to close, by the red light LIT, and goes to RNO to isolate the S/G.COMMENTS: STEP 6.:[4.e.1]CLOSE IntactS/G MSIVs and MSIV bypass valves.-SAT Cue: When operator dispatches
an AUO to close SG#1 MSIV with
-UNSAT acknowledge
the direction.
Critical Step STANDARD: Operator closes intact S/G MSIVs and verifies their bypasses closed as indicated by blue and green lights LIT on HS-1-11 ,-22,&-29 MSIVs and Green lights LIT on HS-1-147,-148,-149,-150
bypasses.[Ensuring the bypasses closed isnotaJPM critical task since valves are already closed.]COMMENTS: STEP 7.:[4.e.2]Dispatch operator to perform EA-1-1, Closing MSIVs Locally, for-SAT any MSIV or MSIV bypass valve which fails to close.-UNSAT Cue: If operator dispatches
an AUO to close SG#1 MS/V with EA-1-1 acknowledge
the direction.
STANDAR.D:
Operator dispatches
an AUO to close MSIV FSV-1-4 using EA-1-1.COMMENTS: STEP 8.-:[4.e.3]Isolate steam header-SAT*PLACE Condenser steam dumps in OFF*ENSURE steam dump valves CLOSED.-UNSAT STANDARD: Operator verifies Condenser Steam dumps are closed as indicated by Critical Step green position indicating
lights LIT on1-XX-55-4A
and places the handswitch(s)
1-HS-1-1 03A and/or 1-HS-1-1 03B in the OFF position on 1-M-4.COMMENTS:
Job Performance
Checklist:
STEP/ST ANDARD JPM#75AP Page 7 of 10 SAT/UNSAT STEP 9.: CLOSE FCV-47-180, HP Steam Seal Supply Isolation-SAT STANDARD: Operator Verifies Steam seals closed as indicated by green light LIT on-UNSAT 1-HS-47-180
OR AUO dispatched
to close local isolation valve on 1-M-2.Critical Step COMMENTS: STEP 10.: ENSURE FCV-47-181, HP Steam Seal Supply Bypass CLOSED.-SAT-UNSAT STAN.DARD:
Operator Verifies HP steam to MFW pump turbine closed as indicated by green light LIT on 1-HS-47-181
on 1-M-2.COMMENTS: STEP 11..: CLOSE MSR HP Steam supply isolation valves.-SAT-UNSAT STANDARD: Operator closes HP steam to MSRs as indicated by green position indicating
lights LIT on 1-XX-1-145, MSR HP Steam Supply Status, Critical Step on 1-M-2 for each of the valves.Two valves on each of the six MSR's have to be closed from the handswitches
on 1-M-2.COMMENTS: STEP 12.: DISPATCH operator to locally isolate steam header USING EA--SAT 1-4, Local Isolation of the Steam header in the Turb Bldg.-UNSAT C*ue: When operator dispatches
an AUO to isolate steam header USING EA-1-4, acknowledge
the direction and provide feedback that the Critical Step traps have been isolated per EA-1-4.STANDARD: Operator directs AUO to isolate the steam header traps per*EA-1-4, Local Isolation of the Steam Header in Turb.Building.COMMENTS: STEP 13.:[4.e.4]USE intact S/Gs atmospheric
relief for steam dumps.-SAT STANDARD: Operator addresses that the atmospheric
reliefs will now have to use for-UNSAT RCS temp control.COMMENTS:
Job Performance
Checklist:
STEP/ST ANDARD JPM#75AP Page 8 of 10 SAT/UNSAT STEP 14.:[5]MONITOR Ruptured S/G level:-SAT a.CHECK narrow range level greater than 10%[25%ADV]b.WHEN ruptured S/G level is greater than 10%[25%ADV]THEN-UNSAT STOP feed flow to Ruptured S/G.1)STOP feed flow to ruptured S/G 2)ENSURE Turbine Driven AFW LeV for ruptured S/G in CLOSE PULL TO LOCK.Critical Step Cue: IF level is<10%state level is now 15%.STANDARD: Operator continues AFW flow to SG#1 until the level is?: 10%on LIS-3-42, 39, 38.THEN the*AFW flow is isolated to the SG#1 by closing the MD AFW and TD AFW level control valves.MD AFW valves closed by depressing
the push button on 1-HS-3-164A, then rotating the switch counterclockwise
to the MANUAL or MANUAL BYPASS position and placing switch to RAMP CLOSED TD AFW valve closed by momentarily
placing 1-HS-3-174
to the CLOSE position and pulling out to PULL TO LOCK.(not critical)Note: When valves are closed the green lights on
for SG#1 will be LIT.COMMENTS: STEP 15.:[6]VERIFY Rupture S/G ISOLATED from Intact S/G(s):-SAT a.CHECK either of the following conditions
SATISFIED:
*Rupture S/G MSIVs and MSIV bypass valves CLOSED-UNSAT OR*MSIVs and MSIV bypass valves CLOS*ED on Intact S/Gs to be used forcooldown.
STANDARD: Operator determines
the intact S/G MSIVs are by the green lights LIT on handswitches
1-HS-1-11 A, 1-HS-1-22A, and 1-HS-1-29A.
Determines
intact S/G MSIV bypasses are closed by green lights LIT on 1-HS-1-148, 1-HS-1-149,1-HS-1-150
COMMENTS: STEP 16.: b.Check S/G#1 or#4 S/G ruptured.-SAT STANDARD: Operator determines
S/G#1 is ruptured and continues to thenextsub--UNSAT step (6.c.).COMMENTS:
Job Performance
Checklist:
STEP/STANDARD
JPM#75AP Page 9 of 10 SAT/UNSAT STEP 17.: c.Check TDAFW pump steam supply from rupturedS/G
-SAT ISOLATED:*FCV-1-15 (S/G#1)or FCV-1-16 (SIG#4)CLOSED.-UNSAT STANDARD: Operator verifies FCV-1-15 closed by GREEN light LIT on handswitch.
1-HS-1-15A on1 (Closed earlier in the J PM)COMMENTS: STEP 18.:[7]CHECK Ruptured S/G pressure greater than 550 psig (Unit 1)-SAT or 425 psig (Unit 2)-UNSAT STANDARD: Operator determines
the ruptured S/G (S/G#1)is greater than 500 psig as indicated on 1-PI-11-2A, 1-PI-11-2B, and 1-PI-11-5 COMMENTS: STEP.19.: Notify SRO that the#1S/G is isolated.-SAT STANDARD: Operator*informs
SRO that he/she is ready to determine the Target Core-UNSAT Exit Thermocouple
temperature.
Stop Time__COMMENTS: END OF JPM
Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be*performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be sati*sfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the han*dout sheet I provided you.IN,ITIAl CONDITIONS:
Unit 1 has experienced
a SGTR.A manual safety injection was initiated and E-O implemented.
E-O and ES-O.5 have been completed and a transition
to E-3 has been
Steps 1 through 3 of E-3 have been completed and S/G#1 has been identified
as the ruptured S/G.INITIATING
C*.UES: You are the eRO and are directed to continue with the actions/responses
of E-3, beginning at Step 4.Inform theSROwhen
you are ready to determine the Target Core Exit Thermocouple
temperature.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY PROCEDURE E-3 STEAM GENERATOR TUBE RUPTURE Revision 17 QUALITY RELATED D.A.PORTER PREPARED/PROOFREAD
BY:_.........................
RESPONS1BLE
ORGANIZATION:
OPERATIONS
w.T.LEARY EFFECTIVE DATE: 10/20107 REVISION DESCRIPTION:
Updated title of EA-201-3
Clarified guidance on initiating
cooldown with S/G atmospheric
relief valves in Substep 8.c.RNO (07001129).
Reworded Substep 4.e RNO for PER 127171 (07001167,07001333,07001569).
This procedure contains a Foldout Page and a Handout Page (2 copies).
SQN STEAM GENERA TOR TUBE RUPTURE Rev.17 FOLDOUT PAGE 51 REINITIATION
CRITERIA IF 81 has been terminated
AND either of the following conditions
occurs:*ReS subcooling
based on core exit TICs less than 40 of, OR*Pressurizer
level CANNOT be maintained
greater than 10%[20%ADV], THEN a.ESTABLISH ECCS flow by performing
one or both of the following:
*ESTABLISH CePIT flow as necessary USING Appendix C*START CCPs or 51 pumps manually as necessary.
b.GO TO ECA-3.1, SGTR and LOCA-SubcooJed Recovery.EVENT DIAGNOSTICS
*IF both trains of shutdown boards deenergized, THEN GO TO ECA-D.O, Loss of All AC PoweL*IF any S/G pressure dropping in an uncontrolled
manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isoiation.
*IF any Intact S/G has level rising in an uncontrolled
manner OR has abnormal radiation, THEN STOP any deliberate
ReS cooldown or depressurization
and GO TO E-3 Step 1.TANK SWITCHOVER
SETPOINTS*IF CST level less than 5%, THEN ALIGN AFW suction to ERCW.*IF RWST level less than 27%, THEN GO TO ES-1.3, Transfer to RHR Containment
Sump.Page 1a of 41
SQN STEAM GENERA TOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 1 of3 STEP I ACTION FOP FOP FOP FOP FOP 1.1.b RNO 2.3.3.a RNO 4.b.RNO 5.a RNO S.b 8.b.8.c.6)IF 51 has been terminated
AND either of the following conditions
occurs:*ReS subcooling
based on core exit TICs less than 4CPF OR*PZr level CANNOT be maintained
greater than 10&deg;.!c>[20%ADV}, THEN ESTABLISH ECCS flow by performing
one or both of the following:
*ESTABLISH CePIT flow as necessary USING Appendix C*START CCPs or 81 pumps manually as necessary.
GO TO ECA-3.1.IF any S/G pressure dropping in an uncontrolled
manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation.
IF any Intact S/G has level rising in an uncontrolled
manner OR has abnormal radiation, THEN STOP any deliberate
ReS cooldown or depressurization
and GO TO E-3 Step 1.IF CST level less than 5%, THEN ALIGN AFW suction to ERCW.IF RWST leve'less than 270/0, THEN GO TO ES-1.3, Transfer to RHR Containment
Sump.MONITOR at least one Rep RUNNING.(If all Reps stopped)WHEN step 32 completed OR E-3 exited, THEN RESUME monitoring
ruptured loop T-cold.MONITOR Rep trip criteria:*At least one CCP or 81 pump RUNNING AND ReS pressure less than 1250 psig*MONITOR indications
of Ruptured 8/G(s).WHEN ruptured 8/G(5)identified, THEN PERFORM Steps 4 through 8.WHEN Ruptured S/G(s)pressure less than 1040 psig, THEN ENSURE S/G atmospheric
relief closed.MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10%[250/0 ADV].WHEN Ruptured S/G level greater than 10%[250/0 ADV], THEN STOP feed flow to ruptured S/G.WHEN ReS pressure less than 1960 psig, THEN BLOCK low steamline pressure 51.WHEN T-avg less than 540&deg;F, THEN BYPASS steam dump interlock.
Page 1b of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 2 of3 STEP B.d ACTION WHEN core exit TICs less than target temperature, THEN 1)STOP ReS cooldown.2)MAINTAIN core exit TICs less than target
9.a.(if Intact S/G level Jess than 10%[25%ADV])RNO MAINTAIN total feed flow greater than 440 gpm and 16.c UNTIL level greater than 100/0[250/0 ADV]in at least one S/G..9.b MAINTAIN Intact S/G narrow range levels between 20%[250/0 ADV]and 50%.10.MONITOR pressurizer
PORVs and block valves: 12.MONITOR AC busses energized from start busses.15.d.MONITOR ReS pressure greater than 300 psig..16.d.MAINTAIN core exit TICs less than target temperature.
17.(if ruptured S/G pressure dropping)RNO MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):*MAINTAIN ReS cooldown rate less than 10CfF/hr.19.d.CONTINUE ReS depressurization
UNTIL any of following conditions
satisfied:
and*Both of the following:
20.b.1)ReS press less than ruptured S/G pressureAND
2)Pressurizer
Jevel greater than 10%[200/0 ADV]OR*Pressurizer
level greater than 65%OR*ReS subcooling
based on core exit TICs less than 4CfF.21.RNO (if ReS pressure dropping)MONITOR for indication
of leakage from pressurizer
PORV.26.CONTROL charging flow to maintain pressurizer
level..27.MONITOR ECCS flow NOT required: a.ReS sUbcooling
based on core exit TICs greater than 40 of b.Pressurizer
Jevel greater than 10%[20 0 h ADV].29.MONITOR if letdown can be established.(pzr level greater than 20 0 h[35%ADV])31.8 WHEN ReS pressure is less than 700 psig, RNO THEN ISOLATE CLAs.Page1cof41
SQN STEAM GENERATOR TUBE RUPTURE E..3 Rev.17 HANDOUT Page 3 of3 STEP ACTION 32.CONTROL ReS pressure and charging flow to minimize ReS-to-secondary
leakage: RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL RISING LEVEL DROPPING GREATER THAN 84%[80%ADV]AND STABLE PZRLEVEL*RAISE charging*RAISE charging*RAISE charging Less than 20&deg;./c>fiow.flow.flow.[35%ADV]*DEPRESSURIZE
*MAINTAIN ReS RCSUSING and Ruptured S/G(s)Substep 32.b.pressures equal.PZRLEVEL*DEPRESSURIZE
*TURN ON*MAINTAIN ReS Between RCSUSING pressurizer
heaters.and Ruptured S/G(s)200/0[35&deg;k>ADV]Substep 32.b.pressures equal.and 50%PZRlEVEL*REDUCE charging*TURN ON*MAINTAIN ReS Between flow.pressurizer
heaters.and Ruptured S/G(s)50%and 65%*DEPRESSURIZE
pressures equaL RCSUSING SUbstep 32.b.Greater than 650/0*REDUCE charging*TURN ON*MAINTAIN ReS flow.pressurizer
heaters.and Ruptured S/G(s)pressures equal.32.c.MONITOR ReS pressure less than 1040 psig.34.MONITOR if containment
spray should be stopped.(pressure less than 2rO psig)35.MONITOR if containment
vacuum control should be returned to normal: (less than 1.0 psig).38.MAINTAIN pressurizer
at saturation
temperature
for ruptured S/G pressure USING pressurizer
heaters.41.MONITOR Rep status.(Rep#2 running)41.a.4)MONITOR natura'circulation
Of NO Rep can be started).RNO 42.MONITOR jf source range channels should be reinstated.(IRM flux less than 10-4 0/0)42.f.WHEN shutdown monitor ALARM LEOs darkAND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.[M13]Page 1d of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 1 of3 STEP]FOP FOP FOP FOP FOP 1.1.b RNO 2.3.3.a RNO 4.b.RNO 5.a RNO 5.b 8.b.ACTION IF 81 has been terminated
AND either of the foJJowing conditions
occurs:*ReS subcooling
based on core exit TICs less than 40'F OR*pzr level CANNOT be maintained
greater than 10%[20%ADV], THEN ESTABLISH ECCS flow by performing
one or both of the following:
*ESTABLISH CePIT flow as necessary USING Appendix C*START CCPs or SI pumps manually as necessary.
GO TO ECA-3.1.IF any S/G pressure dropping in an uncontrolled
manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation.
IF any Intact S/G has level rising in an uncontrolled
manner OR has abnormal radiation, THEN STOP any deliberate
Res cooldown or depressurization
and GO TO E...3 Step 1.IF CST level less than 50/0, THEN ALIGN AFW suction to ERCW.IF RWST level Jess than 27&deg;ftJ, THEN GO TO ES-1.3, Transfer to RHR Containment
Sump.MONITOR at least one Rep RUNNING.(If all Reps stopped)WHEN step 32 completed OR E..3 exited, THEN RESUME monitoring
ruptured roop T-cold.MONITOR Rep trip criteria:*At least one CCP or 81 pump RUNNING AND ReS pressure less than 1250 psig.MONITOR indications
of Ruptured S/G(s).WHEN ruptured S/G(s)identified, THEN PERFORM Steps 4 through 8.WHEN Ruptured S/G(s)pressure less than 1040 psig, THEN ENSURE S/G atmospheric
relief closed.MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10&deg;h,[25%ADV].WHEN Ruptured S/G level greater than 100/0[250/0 ADV], THEN STOP feed flow to ruptured S/G.WHEN ReS pressure less than 1960 psig, THEN BLOCK low steamline pressure 51.B.c.6)WHEN T-avg less than 540&deg;F, THEN BYPASS steam dump interlock.
Page 1e of 41
SQN STEAM GENERA TOR TUBE RUPTURE Rev.17 HANDOUT Page 2 of3 STEP B.d ACTION WHEN core exit TICs less than target temperature, THEN 1)STOP ReS cooldown.2)MAINTAIN core exit TICs less than target temperature.
9.a.(if Intact S/G Jevelless than 100/0[25%ADV])RNO MAINTAIN total feed flow greater than 440 gpm and 16.c UNTIL level greater than 100/0[250/0 ADV]in at least one9.b 10.12.15.d.16.d.17.RNO 19.d.and 20.b.21.RNO 26.27.29.31.a RNO MAINTAIN Intact S/G narrow range levels between 20%[25%ADV]and 50%.MONITOR pressurizer
PORVs and block valves: MONITOR AC busses energized from start busses.MONITOR Res pressure greater than 300 psig.MAINTAIN core exit TICslessthan target temperature.(if ruptured S/G pressure dropping)MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):*MAINTAIN ReS cool down rate less than 10QJF/hr, CONTINUE ReS depressurization
UNTIL any of following conditions
satisfied:
*Both of the following:
1)ReS press less than ruptured S/G pressureAND
2)Pressurizer
Jevel greater than 10%[20%ADV]OR*Pressurizer
level greater than 650/0 OR*ReS subcooling
based on core exit TICs less than 4CfF.(if ReS pressure dropping)MONITOR for indication
of leakage from pressurizer
PORV.CONTROL charging flow to maintain pressurizer
level.MONITOR ECCS flow NOT required: a.ReS subcooling
based on core exit TICs greater than 40 of b.Pressurizer
level greater than 10%[20%ADV].MONITOR if letdown can be established.(pzr level greater than 20%[35&deg;10 ADV])WHEN ReS pressure is less than 700 psig t THEN ISOLATE CLAs.Page 1f of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 3 of 3 STEP ACTION 32.CONTROL ReS pressure and charging flow to minimize RCS-to-secondary
leakage: RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL RISING LEVEL DROPPING GREATER THAN 84%[80%ADV]AND STABLE PZRLEVEL*RAISE charging*RAISE charging*RAISE charging Less than 20%flow.flow.flow.[35%AD\/]*DEPRESSURIZE
*MAINTAIN ReS Res USING and Ruptured S/G(s)Substep 32.b.pressures equal.PZRLEVEL*DEPRESSURIZE
*TURN ON*MAINTAIN ReS Between Res USING pressu rizer heaters.and Ruptured S/G(s)200/0[35%ADV]Substep 32.b.pressures equal.andPZR LEVEL*REDUCE charging*TURN ON*MAINTAIN ReS Between flow.pressu rizer heaters.and Ruptured S/G(s)50%and 650/0*DEPRESSURIZE
pressures equal.RCSUSING Substep 32.b.Greater than 65%*REDUCE charging*TURN ON*MAINTAIN ReS flow.pressurizer
heaters.and Ruptured S/G(s)pressures equal.32.c.MONITOR ReS pressure less than 1040 psig.34.MONITOR if containment
spray should be stopped.(pressure less than 2.0 psig)35.MONITOR if containment
vacuum control should be returned to normal: (less than 1.0 psig).38.MAINTAIN pressurizer
at saturation
temperature
for ruptured S/G pressure USING pressurizer
heaters.41.MONITOR Rep status.(Rep#2 funning)41.a.4)MONITOR natural circulation (if NO Rep can be started).RNO 42.MONITOR if source range channels should be reinstated.(lRM flux less than 10-4%)42.t WHEN shutdown monitor ALARM LEDs darkAND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.[M13]Page 19 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 1.0 PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture.2.0 SYMPTOMS AND ENTRY CONDITIONS
2.1 ENTRY CONDITIONS
E-O Reactor Trip or Safety Injection:
*Secondary radiation.
*S/G level rising in an uncontrolled
manner.E-1, ES-1.2, and ECA-2.1 Foldout Page*S/G level rising in an uncontrolled
manner..E-1 ES-1.2 E-2 ES-3.1 ES-3.2 ES-3.3 Loss of Reactor or Secondary Coolant:*Secondary radiation.
*S/G level rising in an uncontrolled
manner.Post LOCA Cooldown and Depressurization:
*S/G level rising in an uncontrolled
manner.Faulted Steam Generator Isolation:
*Secondary radiation.
Post-SGTR Cooldown Using Backfill:*S/G level rising in an uncontrolled
manner..Post-SGTR Cooldown Using Slowdown:*S/G level rising in an uncontrolled
manner.Post-SGTR Cooldown Using Steam Dump:*S/G level rising in an uncontrolled
manner.(continued
on next page.)Page 2 of 41
SQN STEAM G.ENERA TOR TUBE RUPTURE E..3 Rev.17 2.1 ENTRY CONDITIONS (Continued)
ECA-2.1 ECA-3.1 ECA-3.2 ECA-3.3 FR-H.3 Uncontrolled
Depressurization
of All Steam Generators:
*Secondary radiation.
SGTR and LOCA-Subcooled Recovery:*S/G fevel rising in an uncontrolled
manner.SGTR and LOCA-Saturated Recovery:*S/G level rising in an uncontrolled
manner.SGTR Without Pressurizer
Pressure Control:*S/G level rising in an uncontrolled
manner.*Pressurizer
pressure control restored.Steam Generator High Level:*Secondary Radiation.
3.0 OPERATOR ACTIONS Page 3 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17[STEP I I ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED NOTE This procedure has a foldout page.1.MONITOR at least one Rep RUNNING.IF all Reps are STOPPED, THEN PERFORM the following:
a.SUSPEND monitoring
ruptured loop T-cold indication
on PTS status tree.b.WHEN step 32 is completed OR E-3 is exited J THEN RESUME monitoring
ruptured loop T-cold indication
on PTS status tree.2.MONITOR Rep trip criteria: a.CHECK the following:
a.GO TO Step 3.*ReS pressure less than 1250 psig..........
AND*At least one CCP OR 81 pump RUNNING.b.STOP Reps.Page 4 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 3.MONITOR indications
of Ruptured S/G(s): a.IDENTIFY Ruptured S/G(s)as indicated by any of the following:
*Unexpected
rise in any S/G narrow range level.OR*High radiation from any S/G sample.OR*RADCON survey of main steam Jines and S/G blowdown lines.OR*High radiation on any main steamline radiation monitor.II RESPONSE NOT OBTAINED a.WHEN Ruptured S/G(s)identified, THEN PERFORM Steps 4 through 8.GO TO Step 9.Page 5 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-317 I STEP 11 ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED CAUTION Isolating both steam supplies to the TO AFW pump when it is the only source of feed flow will result in loss of secondary heat sink.*4.ISOLATE flow from Ruptured 8/G(s): 8.ADJUST Ruptured S/G(s)atmospheric
relief controller
setpoint to 87%in AUTO.(1040 psig)b.CHECK Ruptured S/G(s)atmospheric
relief hand switch in P-AUTO and valve(s)CLOSED.c.CLOSE TD AFW pump steam supply from Ruptured S/G FCV-1-15 (S/G#1)or FCV-1-16 (3/G#4).b.WHEN Ruptured S/G(s)pressure less than 1040 psig, THEN PERFORM the following:
1)VERIFY atmospheric
relief CLOSED.2)IF atmospheric
relief NOT closed, THEN CLOSE atmospheric
relief.IF Ruptured S/G(s)atmospheric
relief CANNOT be closed, THEN DISPATCH personnel to close atmospheric
relief USING EA-1-2, Local Control of S/G PORVs.c.IF at least one MD AFW pump running, THEN ISOLATE steam to TD AFW pump USING FCV-1-17 or FCV-1-18.IF TO AFW pump is still running, THEN DISPATCH operator to locally close steam supply from ruptured S/G FCV-1-15 or FCV-1-16.[West Valve Vault Room]d.VERIFY Ruptured S/G(s)blowdown d.CLOSE valve(s).isolation valves CLOSED.(Step continued on next page.)Page 6 of 41
SQN STEAM GENERATOR TUBe RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 4.e.CLOSE Ruptured S/G(s}MSIV and MSIV bypass valve.e.PERFORM the following:
1)CLOSE Intact S/G MSIVs and MSIVbypassvalves.
2)DISPATCH operator to perform EA..1-1, Closing MSIVs Locally, for any MSIV or MSIV bypass valve which fails to close.3)ISOLATE steam header: PLACE condenser steam dumps in OFF.[M-4]*ENSURE steam dump valves CLOSED.[M-4]CLOSE FCV--47-180, HP steam Seal Supply Isolation.
[M-2]*ENSURE FCV-47-181
HP Steam Seal Supply Bypass CLOSED.[M-2]CLOSE MSR HP steam supply isolation varves.[M-2]DISPATCH operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.4)USE Intact S/G(s)atmospheric
relief for steam dump.IF any Ruptured S/G CANNOT be isolated from at least one Intact S/G, THEN GO TO ECA-3.1, SGTR and LOCASubcooled Recovery.-------Page 7 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED CAUTION Feeding a S/G that is Faulted and Ruptured increases the potential for an uncontrolled
ReS cooldown and S/G overfill.This option should NOT be considered
UNLESS needed for Res cooldown.5.MONITOR Ruptured S/G(s)level: a.CHECK narrow range level greater than 10%[25%ADV].b.WHEN ruptured S/G level is greater than 10%[25%ADV], THEN PERFORM the following:
1)STOP feed flow to ruptured S/G.2)ENSURE Turbine Driven AFW LeV for ruptured S/G in CLOSE PULL TO LOCK.a.MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10%[25%ADV].Page 8 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 6.VERIFY Ruptured S/G ISOLATED from Intact S/G(s): I J RESPONSE NOT OBTAINED 7.a.CHECK either of the foUowing conditions
SATISFIED:
*Ruptured S/G MSIVs and MSIV bypass valves CLOSED OR*MSIV(s)and MSIV bypass valve(s)CLOSED on Intact S/G(s)to be used for ReS cooldown.b.CHECK S/G#1 or S/G#4 ruptured.c.CHECK TDAFW pump steam supply from ruptured S/G ISOLATED:*FCV-1-15 (S/G#1)or FCV-1-16 (S/G#4)CLOSED CHECK Ruptured S/G pressure greater than 550 psig (Unit1)or 425 psig (Unit 2).a.DO NOT CONTINUE this procedure UNTIL one of conditions
satisfied.
b.GO TO Step 7.c.DO NOT CONTINUE this procedure UNTIL ruptured S/G steam supply isolated by one of the following:
*FCV-1-15 (S/G#1)or FCV-1-16 (S/G#4)CLOSED OR*FCV-1-17 or FCV-1-18 CLOSED OR*TDAFW pump TRIPPED.GO TO ECA-3.1, SGTR andSubcooled Recovery.----.----IlPage 9 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP](ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED NOTE Blocking low steamline pressure SI as soon as pressurizer
pressure is less than 1960 psig will prevent an inadvertent
MSIV closure and keep condenser available for steam dump.*After the low steamline pressure 81 signal is blocked, main steamline isolation will occur if.the high steam pressure rate setpoint is exceeded.*The 1250 psig Rep trip criterion is NOT applicable
after ReS cooldown is initiated in the following step.8.INITIATE ReS cooldown: a.DETERMINE target core exit TIC temperature
based on Ruptured S/G pressure: Lowest Ruptured Target Core Exit S/G pressure (psig)TiC Temp (OF)1100 or greater 497 1050-1099 492 1000-1049 486 950-999 480 900-949 473 850-899 467 800-849 460 750-799 453 700-749 445 650-699 437 600-649 428 550-599 419 500-549 410 450-499 399 425-449 393 (Step continued on next page.)Page 10 of41
SQN STEAM GENERATOR TUBE RUPTURE E-317 I STEP II ACTION/EXPECTED
RESPONSE 8.b.WHEN Res pressure less than 1960 psig, THEN PERFORM the following:
1)BLOCK low steamline pressure SL 2)CHECK STEAMLINE PRESS ISOUSI BLOCK RATE ISOL ENABLE permissive
LIT.[M-4A, A4]c.DUMP steam to condenser from Intact S/G(s)at maximum achievable
rate: 1)CHECK condenser available:
*C-9 condenser interlock permissive
LIT.[M-4A, E6]*Intact S/G MSIVs OPEN.2)PLACE steam dumps in OFF.3)ENSURE steam dumps in steam pressure mode with demand less than 25%k 4)PLACE steam dumps in ON.5)ADJUST steam dump demand to FULLY OPEN three cooldown valves.6)WHEN T-avg is tess than 540&deg;F, THEN BYPASS steam dump interlock.
II RESPONSE NOT OBTAINEDIF steam dumps NOT available)
THEN OPEN atmospheric
relief valves for Intact S/G(s)RAISE AFW flow to intact S/Gs as necessary to support cooldown.IF local control of atmospheric
reliefs is necessary, THEN DISPATCH personnel to dump steam at maximum achievable
rate USING EA-1-2, Local Control of S/G PORVs.IF NO Intact S/G available, THEN PERFORM the following:
*USE Faulted S/G.OR*GO TO ECA-3.1)SGTR and LOCA-Subcooled Recovery.-------7)RAISE AFW flow to intact S/Gs as necessary to support cooldown.(Step continued on next page.)Page 11 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 8.d.WHEN core exit TICs less than target temperature
determined
in Substep 8.a, THEN PERFORM the following:
1)CLOSE steam dumps or S/G atmospheric
reliefs to stop cooldown.2)REDUCE AFW flow as necessary to stop cool down.MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10%[25 0 ft, ADV]in at least one Intact S/G.3)MAINTAIN core exit TICs less than target temperature
USING steam dumps or atmospheric
reliefs.II RESPONSE NOT OBTAINED Page 12 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 9.MAINTAIN Intact S/G narrow range levels: a.Greater than 10%[25%ADV]b.Between 20%[25%ADV]and 50%.II RESPONSE NOT OBTAINED a.MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10%[25%ADV]in at least one Intact S/G.IF at least 440 gpm AFW flow CANNOT be established, THEN ESTABLISH main feedwater or condensate
flow USING Establishing
Secondary Heat Sink Using Main Feedwater or Condensate
System b.IF level in any Intact S/G continues to rise in an uncontrolled
manner, THEN STOP ReS cool down and GO TO Step 1.--_..Page 13 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 (STEPII ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED CAUTION Any time a pressurizer
PORV opens, there is a possibility
that it may stick open.10.MONITOR pressurizer
PORVs and block valves: a.Power to block valves AVAILABLE b.Pressurizer
PORVs CLOSED c.At least one block valve OPEN.a.DISPATCH personnel to restore power to block valves USING EA-201-1 , 480 V Board Room Breaker Alignments.
b.IF pressurizer
pressure less than 2335 psig, THEN CLOSE pressurizer
PORVs.IF pressurizer
PORV CANNOT be closed, THEN CLOSE its block valve.IF pressurizer
PORV remains open AND associated
block valve CANNOT be closed, THEN GO TO ECA-3.1 , SGTR and LOCA-Subcooled Recovery.---.----c.OPEN one block valve UNLESS closed to isolate an open PORV.Page 14of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 11.RESET 81 signal.12.MONITOR AC busses energized from start busses.13.ENSURE Phase A and Phase B RESET.II RESPONSE NOT OBTAINED ENSURE diesel generators
supplying shutdown boards.WHEN shutdown power restored, THEN ENSURE safeguards
equipment running as necessary.
14.CHECK control air established
to containment:
[Panel 6K and 6L]*1-FCV-32-80
(2-FCV-32-81)
Train A essential air OPEN*1-FCV-32-102
(2-FCV-32-103)
Train B essential air OPEN*1-FCV-32-110
(2-FCV-32-111)
non-essential
air OPEN.ESTABLISH control air to containment
USING EA-32-1, Establishing
Control Air to Containment.
Page 15 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 15.DETERMINE if RHR pumps should be stopped: a.CHECK RHR pump suction aligned from RWST.b.CHECK ReS pressure greater than 300 psig.c.STOP RHR pumps and PLACE in A-AUTO.d.MONITOR ReS pressure greater than 300 psig.II RESPONSE NOT OBTAINED a.GO TO Step 16.b.GO TO Step 16..c.IF pump(s)CANNOT be stopped in A-AUTO t THEN PLACE affected RHR pump(s)in PULL TO LOCK.d.IF ReS pressure dropping uncontrolled, THEN START RHR pumps.Page 16 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 16.CHECK if Res cooldown should be stopped: 8.CHECK core exit TICs less than target temperature
determined
in Substep 8.a.b.CLOSE steam dumps or atmospheric
reliefs to stop cooldown.c.REDUCE AFW flow as necessary to stop cooldown..MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 1 0%[25%ADV]in at least one Intact S/G.d.MAINTAIN core exit TICs less than target temperature
USING steam dumps or atmospheric
reliefs.II RESPONSE NOT OBTAINED 8.DO NOT CONTINUE this procedure UNTIL core exit TICs less than target temperature.
Page 17 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 17.CHECK Ruptured S/G(s)pressure STABLE or RISING.18.CHECK ReS subcooling
based on core exit TICs greater than 60&deg;F.II RESPONSE NOT OBTAINED MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):*SLOWLY DUMP steam from Intact S/Gs*MAINTAIN Res cooldown rate less than 1 GO&deg;F/hr.IF Intact S/G(s)used for cooldown CANNOT be maintained
at least 250 psi below ruptured S/G(s)r THEN GO TO ECA-3.1 t SGTR and LOCA...Subcooled Recovery.---..---GO TO ECA-3.1, SGTR andSubcooled Recovery.---.-----Page 18 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 19.DEPRESSURIZE
Res to minimize break flow and to refill pressurizer:
a.CHECK normal pressurizer
spray
b.INITIATE maximum available pressurizer
spray.c.CHECK depressurization
rate ADEQUATE.d.CONTINUE depressurization
UNTIL any of thefollowingconditions
SATISFIED:
*Both of the following:
1)ReS pressure less than Ruptured S/G(s)pressure AND 2)Pressurizer
level greater than 10%[20%ADV].OR*Pressurizer
level greater than 65%.OR*Res subcooling
based on core exit TICs less than 40&deg;F.I
NOT OBTAINED a.GO TO Cautions prior to Step 20.c.GO TO Cautions prior to Step 20.(step continued on next page)Page 19 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSEII RESPONSE NOT OBTAINED 19.e.CLOSE spray valve(s): 1)Normal spray valves.1)STOP Reps#1 and 2.IF ReS pressure continues to drop, THEN STOP additional
Rep as necessary.
2)Auxiliary spray valves.2)ISOLATE auxiliary spray line.f.GO TO Caution prior to Step 22.=--Page 20 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 , STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED CAUTION*Depressurizing
the ReS using a pressurizer
PORV may cause PRT rupture with resulting abnormal containment
conditions.
*Excessive cycling of a pressurizer
PORV increases the potential for PORV failure.NOTE Upper head voiding may occur during ReS depressurization
if no Reps are running.This may result in rapidly rising pressurizer
level.20.DEPRESSURIZE
ReS USING one pressurizer
PORV to minimize break flow and to refill pressurizer:
a.CHECK at least one pressurizer
PORV AVAILABLE 8.PERFORM the following to establish auxiliary spray: 1)ENSURE at least one SI pump RUNNING.IF NO 81 pump running, THEN GO TO ECA-3.3, SGTR Without Pressurizer
Pressure Control.---.---2)ENSURE at least one CCP RUNNING.3)CLOSE CePIT inlet valves FCV-63-39 and FCV-63-40.
4)CLOSE CePIT outlet valves FCV-63-25 and FCV-63-26.
5)OPEN charging line isolation valves FCV-62-90 and FCV-62-91.
6)ESTABLISH auxiliary spray USING EA-62-4 r Establishing
Auxiliary Spray.(step continued on next page)Page 21 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 20.a.(Continued)
b.OPEN one pressurizer
PORV UNTIL any of the following conditions
SATISFIED:
*Both of the following:1)ReS pressure less than Ruptured S/G(s)pressure AND 2)Pressurizer
level greater than 10%[200/0 ADV].OR*Pressurizer
level greater than 650/0.OR*ReS subcooling
based on core exit TICs less than 40&deg;F.IF auxiliary spray established, THEN GO TO Step 19.b.
IF auxiliary spray CANNOT be established, THEN GO TO ECA-3.3, SGTR Without Pressurizer
Pressure Control.---..-----(step continued on next page)Page 22 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 20.c.CLOSE pressurizer
PORV.c.CLOSE block valve.d.CLOSE spray valve(s): 1)Normal spray valves 1)STOP Reps#1 andIF ReS pressure continues to drop.THEN STOP additional
Rep as necessary.
I-2)Auxiliary spray valves.2)ISOLATE auxiliary spray line.21.CHECK ReS pressure RISING.CLOSE pressurizer
PORV block valve.IF pressure continues to drop, THEN PERFORM the following:
1)MONITOR the following conditions
for indication
of leakage from pressurizer
PORV:*Acoustic Monitoring
System*Tail pipe temperatures
PRT indications.
2)GO TO ECA-3.1, SGTR andSubcooled Recovery.--------Page 23 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED CAUTION Any delay in terminating
51 after termination
criteria are met may cause Ruptured S/G(s)overfilL 22.CHECK if ECCS flow should be terminated:
a.ReS subcooling
based on core exit a.GO TO ECA-3.1 , SGTR and LOCA-TICs greater than 40&deg;F.Subcooled Recovery.*b.Secondary heat sink: b.IF neither condition satisfied J THEN*Narrow range level GO TO ECA-3.1, SGTR and LOCA-in at least one Intact S/G Subcooled Recovery.greater than 10%[25%ADV]..OR*Total feed flow to S/Gs greater than 440 gpm AVAILABLE.
c.ReS pressure STABLE or RISING.c.GO TO ECA-3.1, SGTR and LOCA-Subcooled Recovery...Pressurizer
level d.GO TO Step 6.greater than 10%[20 0 h ADV].:e-Page 24 of 41
SQN STEAM GENERATOR TUBE RUPTURE E..317 I STEPII ACTION/EXPECTED
RESPONSE 23.STOP the following ECCS pumps: a.STOP 81 pumps and PLACE in A-AUTO.b.CHECK offsite power supplying shutdown boards.c.STOP all BUT one CCP and PLACE in A-AUTO.24" ISOLATE CePIT: 8.CLOSE inlet isolation varves FCV-63-39 and FCV-63-40.
b.CLOSE outlet isolation valves FCV-63-26 and FCV-63...25.II RESPONSE NOT OBTAINED a.IF any 81 pump(s)CANNOT be stopped in A-AUTO, THEN
in PULL TO LOCK.b.ENSURE one CCP in PULL TO LOCK.GO TO Step 24.c.IF CCP CANNOT be stopped inA-AUTO, THEN ENSURE one CCP in PULL TO LOCK.IF cePIT flowpath CANNOT be isolated from MeR, THEN CLOSE affected CePIT valves USING EA-201-3, Operation of Motor..Operated Valves from Outside MeR.Page 25 of 41
SQN STEAM GENERATOR TUBE RUPTURE E*3 Rev.17 I STEP)I ACTION/EXPECTED
RESPONSE 25.ESTABLISH charging flow: a.CLOSE seal water flow control valve FCV-62-89.
b.OPEN charging flow isolation valves FCV-62-90 and FCV-62-91.
G.ENSURE normal or alternate charging isolation valve FCV-62-86 or FeV-62-8S OPEN.d.ESTABLISH desired charging flow USING seal water and charging flow control valves FCV-62-89 and FCV-62-93.
26.CONTROL charging flow to maintain pressurizer
level.II RESPONSE NOT OBTAINED b.IF power available, THEN OPEN affected valve from Rx MOV Board USING EA-201-3, Operation of Motor-Operated
Valves from Outside MeR.Page 26 of 41
SQN STEAM GENERATOR TUBE RUPTURE E..3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 27..MONITOR ECCS flow NOT required:ReS 5ubcooling
based on core exit T/Cs greater than 40 0 F.b.Pressurizer
level greater than 10%[200/0 ADV].II RESPONSE NOT OBTAINED a.ESTABLISH ECCS flow manually by performing
one or both.of the following:
*ESTABLISH CePIT flow as necessary USING App..C.*START CCPs or 81 pumps manually as necessary.
GO TO ECA-3..1, SGTR and LOCASubcooled Recovery.---.---b.CONTROL charging flow to maintain pressurizer
level.IF pressurizer
level CANNOT be maintained, THEN PERFORM the following:
1)ESTABLISH ECCS flow manually by performing
one or both of the following:
*ESTABLISH CePIT flow as necessary USING App.C.*START CCPs or 81 pumps manually as necessary.
2)GO TO
SGTR and LOCA...Subcooled Recovery.---..-.......Page 27 of 41
SQN STEAM GENERATOR TUBE RUPTURE Rev.17 I STEP II ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED 28.CHECK veT makeup control system: a.Makeup set for greater than ReS boron concentration.
b.Makeup set for automatic control.ADJUST controls as necessary.
29.MONITOR if letdown can be established:
a.CHECK pressurizer
level greater than 20 0 k[35%ADV].b.ESTABLISH letdown USING EA-62-5, Establishing
Normal Charging and Letdown.a.GO TO Step 30.b.ESTABLISH excess letdown USING EA-62-3, Establishing
Excess Letdown..Page 28 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17[STEP II ACTION/EXPECTED
RESPONSE 30.DETERMINE if CCP suction can be aligned to VeT: a.CHECK CCP suction ALIGNED to RWST.b.ENSURE VCT level is greater than 20%.c.OPEN VeT outlet valves LCV-62-132
and LCV-62-133
and PLACE in PULL A-P-AUTO.d.CLOSE RWSTvalves
LCV-62-135
and LCV-62-136
and PLACE in PULL A-P-AUTO.e.ENSURE VeT cover gas established
USING EA-O-8, Establishing
VeT Cover Gas.II RESPONSE NOT OBTAINED a.IF ECCS pumps aligned for sump recirculation, THEN EVALUATE terminating
sump recirculation
USING EA-63-6, Terminating
Sump Recirculation.
GO TO Step 31.Page 29 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 31.DETERMINE if CLAs should be isolated: a.CHECK ReS pressure less than 700 psig.b.CHECK the following:
*ReS subcooling
based on core exit TICs greater than 40&deg;F*Pressurizer
level greater than 10%[20%ADV].II RESPONSE NOT OBTAINED a.WHEN ReS pressure is less than 700 psig, THEN PERFORM Substeps 31.b, C J and d.GO TO Step 32.b.GO TO ECA-3.1, SGTR and LOCA...Subcooted Recovery.---....-....I 1 p-c.CHECK power to CLA isolation valves c.DISPATCH personnel to restore AVAILABLE.
power to CLA isolation valves USING EA-201...1, 480 V Board Room Breaker Alignments.
d.CLOSE CLA isolation valves.d.IF power available to affected valve(s), THEN CLOSE affected valve(s)USING EA-201-3 J Operation of Motor-Operated
Valves from Outside MeR.IF any CLA valve CANNOT be closed, THEN VENT unisolated
CLA(s)USING EA-63-1 1 Venting Unisolated
Cold Leg Accumulator.
Page 30 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 32..CONTROL Res pressure and charging flow to minimize RCS-to-secondary
leakage: a.PERFORM appropriate
action(s)from table:]I RESPONSE NOT OBTAINED RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL LEVEL RISING DROPPING GREATER THAN 84%[800/0 ADV]AND STABLE PZR LEVEL Less than 200/0*RAISE charging RAISE charging*RAISE charging[35%ADV]flow.flow.flow.*DEPRESSURIZE
*MAINTAIN ReS Res USING and Ruptured Substep 32.b.S/G(s)pressures equal.Between DEPRESSURIZE
TURN ON MAINTAIN ReS 20%[350/0 ADV]Res USING pressurizer
heaters.and Ruptured andSubstep 32.b.S/G(s)pressures equal.Between*REDUCE charging TURN ON MAINTAIN ReS 50%and 65%flow.pressurizer
heaters.and Ruptured*DEPRESSURIZE
S/G(s)pressures RCSUSING equal.Substep 32.b.Greater than 65%REDUCE charging TURN ON MAINTAIN ReS flow.pressurizer
heaters.and Ruptured S/G(s)pressures equal..(step continued on next page)Page 31 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 32.b.USE normal pressurizer
spray as required by SUbstep 32.a.c.MONITOR ReS pressure less than 1040 psig.33.CHECK at least one Rep RUNNING.I[RESPONSE NOT 081 AINED b.IF letdown in service l THEN ESTABLISH auxiliary spray USING EA-62-4, Establishing
Auxiliary Spray.IF letdown NOT in service OR auxiliary spray CANNOT be established, THEN USE onepressurizerPORV.
c.PERFORM the following:1)MAINTAIN ReS subcooling
based on core exit TICs greater than 40&deg;F.2)DEPRESSURIZE
ReS USING Substep 32.b.UNTIL Res pressure less than 1040 psig.3)MAINTAIN ReS and Ruptured S/G(s)pressures less than 1040 psig.RESUME monitoring
ruptured loop T-cold indication
on PTS status tree..Page 32 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 J STEP I J ACTION/EXPECTED
RESPONSE I'RESPONSE NOT OBTAINED 34.MONITOR if containment
spray should be stopped: 8.CHECK any containrnent
spray pump a.GO TO Step 35.RUNNING.=--b.CHECK containment
pressure b.GO TO Step 35.less than 2.0 psig.=--c.CHECK containment
spray suction c.NOTIFY TSC to determine aligned to RWST.when one or both trains of cntmt spray should be stopped.WHEN directed by TSC, THEN PERFORM Substeps 34.d through 34.f.GO TO Step 35.=--d.RESET Containment
Spray signal.e.STOP containment
spray pumps and PLACE in A-AUTO.f.CLOSE containment
spray discharge valves FCV-72-2 and FCV-72-39.
Page 33 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 35.MONITOR if containment
vacuum control should be returned to normal: a.CHECK containment
pressure less than 1.0 psig.b.ENSURE containment
vacuum relief isolation valves OPEN:[Panel 6K or M-9]*FCV-30-46*FCV-30-47*FCV-30-48.
36.DETERMINE if diesel generators
should be stopped: a.VERIFY shutdown boards ENERGIZED from start busses.II RESPONSE NOT OBTAINED a.GO TO Step 36.=--a.ATTEMPT to restore offsite power to shutdown boards USING EA-202-1, Restoring Offsite Power to 6900 V Shutdown Boards.*1 b.STOP any unloaded diesel generators
and PLACE in standby USING EA-82-1, Placing DIGs in Standby.Page 34 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev, 17 I STEP II ACTION/EXPECTED
RESPONSE 37.DISPATCH personnel to perform EA-O-3 J Minimizing
Secondary Plant Contamination.
38.MAINTAIN pressurizer
liquid at saturation
temperature
for ruptured S/G pressure:*OPERATE pressurizer
heaters as necessary.
II RESPONSE NOT OBTAINED 39.CHECK Rep cooling NORMAL:*Rep CCS flow*Rep seal injection flow.ESTABLISH cooling to Reps USING EA-68-3, Establishing
Rep Cooling.Page 35 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 III ACTION/EXPECTED
RESPONSE 40.DETERMINE jf Rep seal return flow should be established:
a.VERIFY Rep seal injection flow established.
b.VERIFY CCS cooling to seal water heat exchanger NORMAL:*SEAL WATER HX OUTLET FLOWITEMP ABNORMAL alarm DARK.[M-27B-B, A6 (M-27B-D, A7)].c.ENSURE the following:
*VeT pressure greater than 13 psig.[M-6]*RCDT pressure[O-L-2]less than VeT pressure.d.OPEN seal return isolation valves FCV-62-61 and FCV-62-63.
II RESPONSE NOT OBTAINED a.GO TO Step 41.b.ESTABLISH CCS cooling to seal water heat exchanger.
IF CCS cooling to seal water heat exchanger CANNOT be established, THEN GO TO Step 41.c.GO TO Step 41.Page 36 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP I I ACTION/EXPECTED
RESPONSE II RESPONSE NOT OBTAINED CAUTION NOTE Loss of all Rep seal cooling may cause Rep seal damage and will require a TSC status evaluation
prior to restarting
affected Reps.Loop 2 Rep and associated
spray valve will provide adequate spray flow for Res pressure control.If Loop 2 is not available, all three remaining Reps may be required to ensure adequate spray flow" 41.MONITOR Rep status: a.CHECK Rep#2 RUNNING.a.ATTEMPT to start Rep(s)to provide normal pzr spray: 1)IF all Rep seal cooling has preViously
been lost l THEN NOTIFY TSC to initiate Rep restart status evaluation.
2)IF RVLIS upper range indication
less than 104%, THEN PERFORM the following:
RAISE pressurizer
level to greater thanOR until level stops rising..RAISE ReS subcooling
based on core exit TICs to greater than 76&deg;F.OPERATE pzr heaters as necessary to raise pzr liquid temperature
to saturation.
3)ESTABLISH conditions
for starting RCP(s)USING EA-68-2, Establishing
Rep Start Conditions.(step continued on next page)Page 37 of 41
SQN STEAM GENERATOR TUBE RUPTURE E*3 Rev.17 I STEPII ACTION/EXPECTED
RESPONSE 41.(Continued)
b.STOP RCP(s)NOT needed for normal pressurizer
spray.I, RESPONSE NOT OBTAINED 4)IF Rep start conditions
established, THEN START Rep#2 (if available)
OR Reps#1" 3 t and 4.IF NO Rep can be started, THEN MONITOR natural circulation
USING EA-68-6, Monitoring
Natural Circulation
Conditions.
IF natural circulation
CANNOT be verified, THEN RAISE steam dump rate.Page 38 of41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 42.MONITOR if source range channels should be reinstated:
a.CHECK intermediate
range flux less than 10-4%power on operable channels.b.CHECK source range channels REINSTATED.
c.SELECT one SRM and one IRM on NR-45 recorder.d.ENSURE audio count rate operation.
e.RESET shutdown monitor alarm setpoints.
[M-13]f.WHEN shutdown monitor ALARM LEOs dark AND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.[M-13]43.SHUT DOWN unnecessary
plant equipment:
REFER TO O-GO..12, Realignment
of Secondary Equipment Following ReactorlTurbine
Trip.II RESPONSE NOT OBTAINED a.GO TO Step 43.b.REINSTATE source range channels by simultaneously
placing both SRM TRIP RESET-BLOCK
switches to RESET position.[M-4]Page 39 of 41
SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED
RESPONSE 44.PERFORM EA-O-9, Post Trip Administrative
Requirements
and Recovery Actions.II RESPONSE NOT OBTAINED NOTE Backfill method is slow but preferred since it minimizes radiological
releases and facilitates
processing
of contaminated
reactor coolant.Slowdown method is slow but minimizes radiological
releases and eliminates
boron dilution and secondary chemistry effects on ReS.Steam dump method is fast but may involve ra dialogical
releases and water hammer concerns (if water exists in the steamlines).
45.DETERMINE appropriate
post-SGTR cooldown method: a.SELECT appropriate
procedure:
ES-3.1, Post-SGTR Cooldown Using Backfill.OR ES-3.2, Post-SGTR Cooldown Using Slowdown.OR*ES-3.3, Post-SGTR Cooldown Using Steam Dump.b.GO TO selected procedure.
--_l1li"---
END Page 40 of41
SQN STEAM GENERATOR TUBE RUPTURE APPENDIX C ESTABLISHING
CePIT FLOW E-3 Rev.17 Page 1 of 1 1.ENSURE CCP suction aligned to one of the following:
*RWST with level greater than 27&deg;j{, OR*RHR pump discharge USING ES-1.3, Transfer to RHR Containment
Sump.2.CLOSE charging flow isolation valves FeV-52-S0 and FCV-62-91.
3.OPEN CePIT outlet valves FCV...63-26 and FCV-63-25.
4.OPEN CePIT inlet valves FCV-63-39 and FCV-63-40.
END OF TEXT Page 41 of 41 o o o o o
PR*EPAREDI
REVISED BY: JPM 22-AP2 Page 1 of 18 Rev 3 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE
MEASURE B.1.f JPM 22-AP2 CALIBRATE POWER RANGE NUCLEAR INSTRUMENTATION
Date/VALIDATED BY:*APPROVED BY: (Operations
Training Manager)Date/Date!CONCURRED:
**(Operations
Representative)
Date/*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM,or individual
step changes that do not affect the flow of the JPM.**Operations
Concurrence
required for new JPMs and changes that affect the flow*of the JPM (if not driven by a procedure revision).
JPM 22-AP2 Page 2 of 18 Rev 3 I NUCLEAR TRAINING REVISION/USAGE
LOG REVISION DESCRIPTION
OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 Created from JPM 22.Y 8/2/04 All MG Croteau 1 Updated References
N 10/5/05 All JJ Tricoglou 2 Updated References.
Minor format N 2/15/07 All RH Evans changes.3 Added detail to steps and standards Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.
JPM 22-AP2 Page 3 of 18 Rev 3 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE
MEASURE Task: Calibrate the Power Range Nuclear Instrumentation
JAITA task:#0150050201
KIA Ratings: 015000 A 1.01 (3.5-3.8)015020 G13 (3.3-3.6)(RO)015020 G9 (3.4-3.3)015000 A4.02(3.9-3.9)Task Standard: 1)EaCh channel of Power Range instrumentation (on its power range"A" drawer)will indicate within acceptance
'criteria tolerances
of the calorimetric.
2)The unit is not tripped by a power range neutron flux rate trip.Evaluation
Method: Simulator__X__In-Plant---===================================================================================
Performer:
Performance
Rating: SAT Evaluator:
NAME UNSAT SIGNATURE Performance
Time DATE Start Time---Finish Time------===================================================================================
COMMENTS
JPM 22-AP2 Page 4 of 18 Rev 3 SPECIAL INSTRUCTIONS
TO EVALUATOR:
1.Sequenced steps identified
by an"s" 2.AnyUNSAT requires comments 3.This task is to be performed using the simulator in IC#16.[Rx Power should be100 0/0]4.MANUALLY ADJUST N-41 and N-43 power to between 100.5 and 101.00/0.ENSURE all other NIS reactor power indications
are between 99.5 and 100.50/0.5.Ensure operator performs the following required actions for SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.27 min Local__
Tools/Equipment/Procedures
Needed: 0-SI-OPS-092-078.0, Sections 3.0, 6.1,6.2, Appendix D References:
l-itle Rev No, 1.0-SI-OPS-092-078.0
Power Range Neutron Flux Channel Calibration
By 18 Heat Balance Comparison
==========================="==================================================
READ TO OPERATOR Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understandyourassigned
task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.The unit is at steady state conditions
with all NIS channels and LEFM operable.INITIATING
CUES: 1.You are theCRO and the US has directed you to perform.O-SI-OPS-092-078.0.
2.Section 4.0 of 0-SI-OPS-092-078.0
has been completed.
3.Notify the US when the Sihas been completed and any necessary adjustments
have been made.
Job Performance
Checklist STEP/ST ANDARD JPM 22-AP2 Page 5 of 18 Rev 3 SAT/UNSAT STEP 1.: Obtain the appropriate
procedure.
SAT UNSAT STANDARD: Operator identifies
O-SI-OPS-092-078.0and
goes to section 6.0"Performance".COMMENTS: STEP 2.:[1]VERIFY availability
of LEFM calorimetric
power:[aj CHECK
s.tatus NO:Rf\{AL:Ctn ICS{NSSS.and BOP}CUrT*:'ot Calcritnetrrc
Data s.cre;e.:rL
"{ESo 0[bI CHECK LEFfs{Core Themlal Pewer (ICS point 0211,s)
{gre'en)data.YES N{)o[c]CHEC.K LEFrit1lv1FVV
he,ader te:rrq:<*<rature
{ICS point T85C2M.A.)
greater
or equai to 2SD:::Fv YES N:Q a STANDARD: Operator pulls up LEFM ICS screen and points, then annotates procedure that LEFM calorimetric
power is available.
COMMENTS: Start Time__SAT UNSAT
Job Performance
Checklist STEP/ST ANDARD STEP 3.:[2]IF LEFM calorimetric
power NOT available OR ICScomputer
NOT available, THEN....PERFORtA the
Ie]IF LEFM
power CANNOT be rest.ored in tirT:i:e to OOP1:lplete
this
THEN'PERFOR'".the
....:1.: R.EDUGE reactor
(341*1 ()i1VJt).or;'ess U.S1NG V t 11-8{if d"iaHah4e}
orN:;SA 2..:WHE\N reactor
is less*
THEN CONTINUE this.
'U*s;in:g alternate power in d5cati ens as 5.p;<JE<c::me(i
be!kt\Y.STANDARD: Operator marks the 4 sub steps (a, b, c.1,&c.2)N/A because the LEFM was determined
to be available in the previous step.COMMENTS: JPM 22-AP2 Page 6 of 18 Rev 3 SAT/UNSAT SAT UNSAT
Job Performance
Checklist sTEP/sT ANDARD STEP 4.:[3]DETERMINE reactor core power level by performing
the applicable
appendix below.RCS AT greater.and A CJ LE F't1:CJC*re the:rm:3il (U211,B).avajlabre'
{step (1]
criteria r;l:E:t)RGS ATbetw*een
and 4D%.and:6 a LE F}t1-(;SDre tnennal (U211
av*ailabtE'
xG.ST grea,:er than
C Cl LEF't.1:core
pC{ttef (:U2118)N::DT a'Jailab4e
:but tcs
U1118 is available RG.S AT 9lreater than
[)Cl lCS corE: therrnaI pCtl.i"er indic:aiicn (U1 t tS and U2t tEl NOT
AND RECORD below the (N/A power if using printout from ICS)0/0 Rated Core Thermal Power=0/0 Cue: Inform the operator that the ICS printer is not available.
Cue: If candidate asks if the engineering
procedure O-PI-SXX-OOO-022.2
has been performed, state that it has not been performed.
STANDARD: Operator determines
Appendix A.is applicable
to determine the reactor power level.COMMENTS: JPM 22-AP2 Page 7 of 18 Rev 3 sAT/U N SAT SAT UNSAT
Job Performance
Checklist STEP/STANDARD
EVALUATOR NOTE: The following steps are from Appendix A.STEP 5.:[1]ENSURE S/G blowdown flows are updated by performing
the following functions onlCS:[a]SELECT"NSS&BOP".[b]SELECT"CALORIMETRIC
FUNCTION MENU".[c]SELECT"UPDATE OPERATOR ENTERED SLOWDOWN FLOW" P;8RFORtAone
0:1 the falhrrt#lfrt:Q
opbonnot used)1IF using:CC411puter
if 2:26: tAl SiG T o1:a!&sect;Slo&#xa5;/dcvln
flo'vi, THEt4 fa)'VERlfY
v-a.:j::!j':E
is.updLa'bng (chang;:iniQ
vaiktes)..(b)If
po:j::nt is. ulpdatingL
J T:HE.N NO TIFY}t1 that pc:int is nc4 upda.tlrtg
c;nd inltia1eVVCt
..('a]RECORD
fo;!SIG
fktVI:: JPM 22-AP2 Page 8 of 18 Rev 3 SAT/U N SAT SAT UNSAT[ReS LOOP 2 3 4 BLO:WI)O\'VN
flOW
FI-1i-"164
j Ib]i E:t4 SU RE
uDvrs.above entered ICS..VIAIT a minirnun1 e:f to minut.es to allow prograrTl b,:;a.ccurately
Jialue..Cue: The blowdown flow point is updating and manual blowdown flows are not required.STANDARD: Operator determines
blowdown flow is updating and marks substeps 1 b, all of substep 2 N/A.COMMENTS:
JPM 22-AP2 Page 9 of 18 Rev 3 Job Performance
Checklist STEP/ST AN*DARD STEP 6.:[2]SELECT"DISPLAY CURRENT CALORIMETRIC
DATA" on ICS Calorimetric
menu AND PERFORM one of the following:
SAT/UNSAT SAT UNSAT_____M\&#xa5;t._----OR*rbl P\RlNT po\ver ie'V"'el a:nd
AND*ATTACH re[fl*Oft to th@s instnJ'ctJcn.
Cue: Inform the operator that the printer is not available.
STANDARD: Operator records U2118 and U1127 values.COMMENTS: EVALUATOR NOTE: The operator should transistion
back to section 6.1 at the completion
of Appendx A.The following steps are from Section 6.1.STEP 7.:[4]RECORD"AS FOUND" power level from each of the four NIS A Channel drawers.P'OW:EjRRAN*GE
CHANt*rEt
():,
1\r4-42
)
{X.I-@:2-a001B)
:N-44 tX:I-2i2-5GrTIf6;B
J
N.'IS POl.VER t.%}: SAT UNSAT STANDA*RD:
Operator records NIS power range readings from the A channel drawers on 1-M-13 on1-XI-92-5005B,50068, 50078, and 50088 COMMENTS:
Job Performance
Checklist STEP/STANDARD
STEP 8.:[5]COMPARE NIS indication
with core thermal power level.[a]CHECK appropriate
box to indicate whether the followingfound" ACCEPTANCE
CRITERIA were satisfied.
ACCEPTAN,CE
CRITERiA: The indicatedNlS
power le'tel recorded i:n st$p[4]is equal10 the core thermal: pewer
recorded iin step{31 as W-s*tedon the wtihin+/-2.0
JPM 22-AP2 Page 10 of 18 Rev 3 SAT/UNSAT SAT UNSAT NJSGhanneoI
N-41 NmSChannet
N4.2 N:::S Channe*;l N-43 N:::S Channe:i N*-44 YES Cl o o o filA a a Q: Q: STANDARD: Operator CHECKS to determine if NIS channels are within2%.Then, Checks YES for all NIS channels.COMMENTS: STEP 9.:[b]IF any NIS channels were inoperable
during the performance
of this instruction, THEN: NOTIFY applicable
unit SRO that this SI must be performed on all inoperable
NIS channels when they are returned to service.SAT UNSAT STANDARD: Since all were operable per the initiating
conditions, the operator marks this substep N/A.COMMENTS: STEP 10.:[6]VERIFY that all NIS channel indications
are within+/-3 percent of the determined
core thermal power level.YES NO Q a STAN.DARD:
Operator checks the YES*box.COMMENTS: SAT UNSAT
Job Performance
Checklist STEP/ST AN DARD JPM 22-AP2 Page 11 of 18 Rev 3 SAT/UNSAT STEP 11.:[7]IF a NIS channel was more than 3 percent in error in the non--SAT conservative
direction (core thermal>NIS)THEN NOTIFY Engineering
to determine if the calibration
error-UNSAT impacts operability
of the NIS high flux trip.STANDARD: Operator marks this step N/A.COMMENTS: STEP 12.:[8]CHECK appropriate
box to indicate whether the following"as-found"-SAT acceptance
criteria were satisfied:
-UNSAT ACCEPTANCE
CRITERIA: The indicated NIS power level recorded in step[4]is less than or equal to 100.5 percent.YES NO NIA N::1S*C;n,.anne::[
N*-41 Q:0 Q Ni:iS e,ho*anne':;
N**-42 U:Q Q N::[SChanne{
N-43 Q:0 Q
N*-4.;0'Q Q STANDARD: The operator checks NO forN-41 and N-43 and checks YES for other 2 channels.COMMENTS: STEP 13.:[9]IF any channel does not meet acceptance
criteria, OR NIS Channel-SAT adjustment
is desired ,THEN PERFORM adjustment
of section 6.2-UNSAT AND/OR REDUCE reactor power not to exceed 100 percent.STANDARD: Operator continues on to section 6.2.COMMENTS:
Job Performance
Checklist STEP/STANDARD
JPM 22-AP2 Page 12 of 18 Rev 3 SAT/UNSAT EVALUATOR NOTE: The following steps are from Section 6.2-SAT STEP 14.:[1]IF calculated
average power in Section 6.1 or on printed copy and differs by more than 30/0 from average RCS delta T, THEN-UNSAT NOTIFY Engineering
to determine the cause.STANDARD: Operator determines
calculated
average power and average delta T does not differ by more than 3%by comparing calculated
average power against delta T from ICS or use 1-M-5 delta T instruments
and N/As this step.COMMENTS: STEP 15.:[2]VERIFY reactor power has remained constant0.5%)since-SAT performance
of section 6.1.-UNSAT STANDARD: Operator ensures power has remained stable since he/she took the readings.COMMENTS: STEP 16.:[3]IF NIS power range channel is inoperable
-SAT THEN REQUEST Instrument
Maintenance
to Bypass inoperable
NIS channel in-UNSAT accordance
with O-PI-IXX-092-001.0.
STANDARD: Operator N/As this step since aU power range instruments
are operable.COMMENTS: STEP 17.:[4]ENSURE all NIS power range channels are operable or bypassed with no-SAT bistables tripped.-UNSAT STANDARD: Operator verifies no bistables tripped bymonitoringTrip
status panel, 1-XX-55-5, bistable lIights on 1-M-5.(Initial conditions
had all channels operable)COMMENTS:
Job Performance
Checklist STEP/ST AN DARD JPM 22-AP2 Page 13 of 18 Rev 3 SAT/UNSAT STEP 18.:[5]ENSURE rod control system is in MANUAL in accordance
with 0-SO-85-1-SAT-UNSAT STANDARD: Operator turns
0, ROD CONTROL MODE SELECTOR, to the MANUAL position.Should refer to
A laminated sheet is available.
COMMENTS: Evaluator Note: Procedure contains a note stating Steps[6J ,through[9J must be completed on one NIS channel before proceeding
to the next channel.Operator must adjust the N-41'and N-43, may choose to adjust all 4 channels.STEP 19.:[6]IF rate trip exists'(or occurs)on the NIS channel being calibrated, THEN-SAT CLEAR that channels trip signal (momentarily
set RATE MODE switch to-UNSAT RESET position)and annunciator
XA-55-6A,."NC-41U or NC-41K NIS POWER RANGE HIGH NEUTRON FLUX RATE," before proceeding
to the next NIS channel.'Trip Cleared Ni,A.N
0 NlSGhanne,*
N-42 U 0 Critical Step N is Ghann
Q;Q
N-44 0:0 STANDARD: Operator verifies NO rate trip signals are inon ANY of the PR and the annunciator
is clear.*CRITICAL PORTION: If rate trip occurs the operator resets it prior to continuing
to the next channel.COMMENTS:
Job Performance
Checklist STEP/STANDARD
STEP 20.:[7]ADJUST gain potentiometer
on associated
channel's power range B drawer to bring that channel's indicated power level to within+/-..5%of the calorimetric
power recorded in section 6.1 or listed on the printed copy.AND JPM 22-AP2 Page 14 of 18 Rev 3 SAT/UNSAT N-41 adjustment
SAT NJS
N41 N ISChanne;;
ti-42 Gh*anne*&sect;N-4.3 ENSURE gain
latch re-engaged.
__J4.djusiment
Required a a a a CI Q U Q UNSAT N-43 adjustment
SAT STANDARD: Operator must adjust N41 and N43 to satisfy criteria.The operator should repeat the above step prior to adjusting the second PRo (only the bold portion of the standard is critical)COMMENTS: STEP 21.:[8]IF fine gain potentiometer
on power range B drawer will not provide enough adjustment
to satisfy the calibration
requirements
of step[7], THEN REQUEST Instrument
Maintenance
to adjust the coarse gain (resistor R312, Coarse Level Adjust)inside the applicable
power range drawer, AND READJUST fine gain potentiometer
to achieve calibration
requirements
specified in step[7].UNSAT Critical StepiSChannefi
t4-41: N
N-42 lSCih.anne*ili
t4-43: N lSChanne1 N-44 It,djustrrtent
Reql1!ired
o o o o STANDARD: Operator marks step as N/a because the fine gain will provide the needed adjustment.
COMMENTS:
Job Performance
Checklist STEP/STAN DARD STEP 22.:[9]IF additional
NIS channel(s)
require calibration, THEN RETURN to step[6]Evaluator note: Procedure step f6]is JPM step 19 STANDARD: Operator may return to step[6]to adjust either N41 or N43 or other 2 channels if desired.After adjustments
to Nls is complete, the operator continues to the next step COMMENTS: STEP 23.:[10]WHEN NI*S adjustments
have been completed, THEN RECORD the"as left" power level from NIS power range channels.POWER RA:NGE
CH,ANN.El NIS POJ'/ER (&#xa3;>/.3}
(;\J-92-5000'8:)
CXJ-92-5007B)
NJ-44 tXi-Q2-5008B
J STANDARD: Operator records the readings from each of the 4 PR Nls.COMMENTS: STEP 24.:[11]IF NIS power range*channel is inoperable, THEN REQUEST Instrument
Maintenance
to remove Bypass on inoperable
NIS channel in accordance
with O-PI-IXX-092-001.0.
STANDARD: Operator NIAs this step since all Nls are operable.COMMENTS: JPM 22-AP2 Page 15 of 18 Rev 3 SAT/UNSAT N-41 adjustment
SAT_UNSAT N-43 adjustment
SAT UNSAT SAT UNSAT SAT UNSAT
Job Performance
Checklist STEP/ST AN DARD JPM 22-AP2 Page 16 of 18 Rev 3 SAT/UNSAT STEP 25.:[12]CHECK appropriate
box to indicate whether the following"as left"-SAT acceptance
criteria were satisfied.
-UNSAT ACCEPTAN:CE
CHITERlA.:
T.he indrc.ated
N IS patNer leve!: recorded in step (1 OJ is wrthin+/-0".5 percent the: cal*oMfmeftrk:
p-o'werieve!
lreoorded in SectonG.1 01'a:s Jisted en the printed copy.YES NlA NWS
N-41 Cl a Q 1-'-.ns Channe:t N-42 U:Q Q Ni:;S ChanneJ N-43 Q Q Q Nl\tS
N-44.a:QSTANDARD: Operator checks YES box for N41, N42, N43,&N44, all being within:!:..5%(of 1 00%).COMMENTS: STEP 26.:[13]IF acceptance
criteria were NOT satisfied for any NIS channel, THEN-SAT NOTIFY Shift Manager that acceptance
criteria were'NOT met and another performance
of this test is necessary,-UNSAT subsequently
action 2 of LCO 3.3.1.1 (Unit 1)orLCO 3.3.1 (Unit 2)must be satisfied if the other performance
does not meet acceptance
criteria.STANDARD: Operator N/As this step.COMMENTS: STEP 27.:[14]RETURN rod control system to AUTO in accordance
with O-SO-85-1.
-SAT Cue: When operator acknowledges
the 3 minute wait in the note preceding the-UNSAT step, Inform the operator that 3 minutes have elapsed.STANDARD: Operator places control rod bank selector"switch
to the AUTO after waiting at least 3 minutes for signal to decay.Should refer to O-SO-85-1.
A laminated sheet is available.
COMMENTS:
Job Performance
Checklist STEP/ST AN DARD JPM 22-AP2 Page 17 of 18 Rev 3 SAT/UNSAT STEP 28.: Notify SRO that the NIS channels have been calibrated.
SAT STANDARD: Operator notifies the SRO that the SI has been completed and all power range nuclear instruments
have been adjusted to meet the acceptance
criteria.COMMENTS: END of JPM UNSAT Stop Time__
CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION
OF TASK)DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating
cues and reports on other actions when directed by you.Ensure you indicate tome when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIO.NS:
The unit is at steady state conditions
with all NIS channels and LEFM operable.INITIATING
CUES: You are the CRO and the US has directed*you to perform 0-SI-OPS-092-078.0.
Section 4.0 of 0-SI-OPS-092-078.0
has been completed.
Notify the US when the 51 has been completed and any necessary adjustments
have been made.
...'""""....................." 1..1'....'...-...,'_"'..-..............
........--..__-.._.__---.-..:.__**_---TV AN STANDARD PROGRAMS AND PROCESSES SURVEILLANCE
TEST PROGRAM , r l SURVEILLANCE
TASK SHEET (STS)Page 1 of 1 SPP-8.2 Date 06-04*2004
Page 25 of 29 SURVEILLANCE
TASK SHEET (ST5)Page Work Order SI Key----,.p.....
'1 Procedure No.0
j Y!1v Title
.
11/Perf.Section\J t , I O.fi.:.>/*r"1/1 il T est Reason
t\(J";",'-;" c:...
Data Sheets--------------i1.I/Due-----.....-.----------i!
V'Extension
rv1ax.Extension--------------!l
Frequency-----------..---,;.....;,-.--!l
EO--------------11
ASME Xl APP Mode--------------11
Performance
---------------il
Operational
Condition
Dry Cask Storage O*Yes 0 No Subsequent
Reviews--------------il
Instruction'
of C (!xl-/pg'ALN'I Dat'e Time Start Date Time Completion
Date Time Test Director/lead
Performer Date (ASME Xl Sis require review within
96 hours).Date Time Independent
Reviewer Date ANII (If required).Date Remark:.,-Copy of STS sent to Scheduling
Initials Date Section No.Men Our.Hrs Section No.Men Our.Hrs Our.Hrs I Our.Hrs SPP-8.2-1[06.04-200
4 1 No.Men No.Men.
!Section k__-Se-eu-*oo---i.Page 1 of 1.TVA 40753[06-20041
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE
INSTRUCTION
O-SI-OPS-092-078.0
POWER'RANGE NEUTRON FLUX CHANNEL CALIBRATION
BY HEAT BALANCE COMPARISON
Revision 18 QUALITY RELATED w.T.LEARY PREPARED/PROOFREAD
BY:
RESPONSI BLE ORGAN IZA TION:_O.;;...;p
.......
O__.N..;;..",;;;,S
_KEITH PERKINS APPROVED BY:-------.---------------
EFFECT'IVE
DATE:03/30/06
LEVEL OF USE: CONTINUOUS
USE REVISION DESCRIPTION:
Revised to add a.note.directing
that consistency
between channels be considered
when determining
if adjust is desired.This is a minor change.THIS PROCEDURE COULD AFFECT REACTIVITY.
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 2 of 33 TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS 2 1.0 INTRODUCTION
4 1.1 Purpose 4 1*.2 Scope 4 1.2.1 Surveillance
Test to be Performed 4 1.2.2 Requirements
Fulfilled 4 1.2.3 Modes 4 1.3 Frequency and Conditions
4 2.*0 REFERENCES*
5 2.1 Performance
*References
5 2.2 Developmental
References
5 3.0 PRECAUTIONS
AND LIMITATIONS
5 4..0 PREREQUISITE
ACTION*S.....................................*........................................................
7 4.1 Preliminary
Actions 7 4.2 Measuring a*nd Test Equipment, Parts, and Supplies 7 4.3 Field Preparations
7 4.4 Approvals and Notifications
7 5.0 ACCEPTANCE
CRITERIA 7
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 3 of 33 TABLE OF CONTENTS Page 2 of 2 Section Title Page 6.0 PERFORMANCE
;.8 6.1 As-Found Data 8 6.2 NIS Channel Adjustment
14 7.0 POST PE.RFORMANCE
ACTIVITY 18 APPENDICES
APPENDIX A: APPENDIX B: APPENDIX C: APPENDIX D: CALCULATION
OF CORE THERMAL POWER LEVEL USING LEFM 19 SUBSTITUTION
OF RCS AT LOW POWER LEVELS
WITH LEFM NOT AVAILABLE)
22 CALCULATION
OF CORE THERMAL POWER LEVEL USING U1118 (>40%WITH LEFM NOT AVAILABLE)
23 CALCULATION
OF CORE THERMAL POWER LEVEL WITH PLANT COMPUTER INOPERABLE (RCST GREATER THAN 400/0)26 SOURCE NOTES 33
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 4 of 33 1.0 INTRODUCTION
1.1 Purpose This Surveillance
Instruction (SI)provides detailed steps for ensuring proper calibration
of the power range neutron flux channels.1.2 Scope 1.2.1 Surveillance
Test to be Performed This Instruction
performs a comparison
between the power level calculated
by the Nuclear Instrumentation
System (NIS)power range neutron flux channels and the"true" power level as determined
by a secondary system heat balance based value.If necessary, the power range channels are adjusted to agree with the"true" power level.This instruction
also verifies availability
of Leading Edge Flow Meter (LEFM)calorimetric
power.1.2.2 Requirements
Fulfilled Performance
of this Instruction
completely
fulfills Technical Specification (TS)Surveillance
Requirement (SR)4.3.1.1.1.8.2 (Table 4.3-1, item 2, note 2)and Technical Requirements
Manual (TR)4.3.3.15.1.
1.2.3 Modes A.Applicable
Mode-1 (above 15 percent power).B.Performance
Mode-1 (above 15 percent power).1.3*Frequency and Conditions
This test must be performed at least once every 24 hours when the reactor power level is greater than 15 percent.[C.3]To ensureNIS accuracy, this test should be performed when directed by O-GO-4 or O-GO-5.In the event that the Plant Computer is unavailable, provisions
have been incorporated
in this procedure to fulfill the SR requirements.
[C.5]
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 5 of 33 2.0 REFERENCES
2.1 Performance
References
O-PI-SXX-OOO-022.2, Calorimetric
Calculation.(Optional)
2.2 Developmental
References
A.SQN Technical Specifications.
B.SPP-8.1, Conduct of Testing C.NP-STD-4.4.7, Attachment
1, Writer's Guide for Technical Documents D.0-PI-NUC-092-082.0, Post Startup NIS Calibration
following Core Load.E.Memo from Reactor EngineeringRIMS S57 941219 934 F.Integrated
Computer System Critical Design Requirements
and Operator's
Guide.3.0 PRECAUTIONS
AND LIMITATIONS
A.Reactor power must remain constant (+/-0.5&deg;/0)during the performance
of Sections 6.1 and 6.2.Itis desirable for any required NIS adjustment
be made promptly during performance
of these sections.B.Average ReS temperature (T avg)should be maintained
within 0.5&deg;F of RCS reference temperature (Tref)'C.Caution should be exercised when adjustingNIS
power range instrumentation
to minimize the potential for a channel trip.D.Only one NIS channel shall be adjusted at a time.If a rate trip occurs, the channel's trip signal and annunciator
on panel XA-55-6A,"NC-41 U or NC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RATE" must be cleared before proceeding
to the next NISchannel.
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 6 of 33 3.0 PRECAUTIONS
AND LIMITATIONS (Continued)
E.Operations
and Engineering
should be notified if larger than normal channel adjustments (as determined
by the SRO)are required to bring the power range channels into alignment with calculated
core thermal power.[C.4]An operability
concern may exist if excessive error in the non-conservative
direction adversely impacts the NIS high flux trip setpoint.The 3%tolerance for calibration
error on the high flux trip setpoints was selected using the extrapolated
error from the 30%power level.F.The reactor cores have been loaded with a low leakage-loading pattern which can affectNIS Reactor Power level indications
such that differences
greater than the Acceptance
Criteria can occur between NIS and true power level.The impact of the NIS non-linearity
due to low leakage loading pattern isin the conservative
direction, since NISindicated
power rises faster than true power during a power increase.0-GO-5 may direct performance
of this procedure to ensure excessive errors in the non-conservative
direction do not exist.During plant restarts, Reactor Engineering
may perform 0-PI-NUC-092-082.0
at 40/0 power to provide an initial NIS correction
for startup.G.Technical Specifications
require aheatbalance
calculation
for adjustment
of theNIS when the Plant is above 15%power within 24 hours.If the Leading Edge Flow Meter (LEFM)is available, ICS point U2118 is required to be used for the heat balance when greater than 15%power (TRM 3.3.3.15).
If LEFM is NOT available, then LoopT data should be used between 15 and 40%power due to potential inaccuracies
in the feedwater-flow venturi heat balance below 40%.If LEFM is NOT avai-Iable
above 40%, then venturi-based
calorimetric
power (U1118)should be used.
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
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Page 7 of 33 J I Unit------4.0 PR"EREQUISITE
ACTIONS Date)'X b!.!.rIiJ(NOTE During the performance
of this Instruction, any"IFITHEN" statement may be marked N/A when the corresponding
stated condition does not OCCUL 4.1 Preliminary
Actions[1]ENSURE Instruction
to be used is a copy of effective version_()Il and Data Package Cover Sheet is attached.!'J{;-4.2 Measuring and Test Equipment, Parts, and Supplies None;4.3 Field Preparations
[1]ENSURE reactor power and RCS average temperature
are stable.4.4 Approvals and Notifications
[1]NOTIFY SRO of test performance.
5.0 ACCEPTANCECRITERIA
A.The indicated"as-found" power level from each operable NIS neutron flux channel must equal the core thermal power level to within+/-2.0%.B.The indicated"as-left" power level from each operable NIS neutron flux channel that was adjusted must equal the core thermal power level to within+/-0.5%.c.If the criteria stated above are NOT satisfied, the SRO shall be notified and Action Requirement
2 of TS Table 3.3-1 satisfied.
D.LEFM shall be used for the plant calorimetric
measurement
for power range NIS calibration
by heat balance comparison.
If this criteria is NOT satisfied, the SRO shall be notified and the applicable
action of TRM 3.3.3.15 shall be entered.
SQN POWER RANGE NEUTRON FLUX
0 CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 8 of 33 Unit------6.0 PERFORMANCE
6.1 As-Found Data Date-----NOTE 1 NOTE 2 The following step determines
if LEFM is available tosatisfyTRM
3.3.3.15.If LEFM is NOT available, operators should notify US, document status and continue with next step.Main feedwater temperature
must be greater than or equal to 250&deg;F for reliable LEFM data.[1]VERIFY availabi-lity
of LEFM calorimetric
power:[a]CHECK LEFM status NORMAL on ICS (NSSS and BOP)Current Calorimetric
Data screen.YES NO o 0[b]CHECK LEFM Core Thermal Power (ICS point U2118)showing good (green)data.YES NO o 0[c]CHECK LEFM MFW header temperature-(ICS point T8502MA)greater than or equal to 250&deg;F.YES NO o 0 ACCEPTANCE
CRITERIA: LEFM is available based upon the indications
above.
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
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Page 9 of 33 Unit------6.1 As-Found Data Date-----NOTE With LEFM unavailable, AFD limit lines in COLR must be made more restrictive
by 1%and Rod Insertion Limit lines in COLR must be raised by 3 steps.These adjustments
are automatically
applied in ICS.[2]IF LEFM calorimetric
power NOT available OR ICS computer NOT available, THEN PERFORM the following:
[a]ENTER applicable
action of TRM 3.3.3.15.[b]ENSURE work order initiated as required.[c]IF LEFM calorimetric
power CANNOT be restored in time to complete this surveillance, THEN PERFORM the following:
1.REDUCE reactor power to 98.7&deg;1b (3411 MWt)or less USING U1118 (if available)
orNIS.2.WHEN reactor power is less than 98.7%, THEN CONTINUE this instruction
using alternate power indications
as specified below.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0
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Page 10 of 33 Unit------6.1 As-Found Data Date-----NOTE If Engineering
has performed 0-PI-SXX-000-022.2, then the applicable
section{s)of
0-PI-SXX-OOO-022.2
may be used in place of Appendix C orO to obtain the current calorimetric
power.[3]DETERMINE reactor core power level by performing
the applicable
appendix below: CONDITION APPENDIX../ReS L1 T greater than 15'%and A 0 LEFM core thermal power (U2118)available (step[1]acceptance
criteria met)RCS L1 T between 15%
and B 0 LEFM core thermal power (U2118)NOT available RCS L1 Tgreater than 40%C 0 LEFM core thermal power (U2118)NOT available but ICS point U1118 is available RCS L1 T greater than 400/0 and D 0 ICS core thermal power indication (U1118 and U2118)NOT available AND RECORD below (N/A power if using printout from ICS):%Rated Core Thermal Power=-----
SQN POWER RANGE NEUTRON FLUX
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 11 of 33 Unit------6.1 As-Found Data (Continued)
Date-----NOTE Data for an inoperable
NISchannelmay
be marked N/A.[4]RECORD"as-found" power level from each of the four NIS power range A channel drawers: POWER RANGE" AS-FOUND" CHANNEL NIS POWER (&deg;10)N-41 (XI-92-5005B)
N-42 (XI-92-5006B)
N-43 (XI-92-5007B)
N-44 (XI-92-5008B)
NOTE The following step is performed to satisfy Tech Specs.[5]COMPARE NIS indication
with core thermal power level.[a]CHECK appropriate
box to indicate whether the following"as-found" acceptance
criteria were satisfied:
ACCEPTANCE
CRITERIA: The indicated NIS power level recorded in step[4]is.equal to the core thermal power level recorded in step[3]or as listed on the printed copy to within+/-2.0 percent.YES NO N/A NIS Channel N-41 0 0 0 NIS ChannelN-42
0 0 0 NIS Channel N-43 0 0 0 NIS Channel N-44 0 0 0 RO orSRO
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Page 12 of 33 Unit------Date-----6.1 As-Found Data (Continued)
[b]IF any NIS channels were inoperable
during the performance
of this Instruction, THEN NOTIFY applicable
unit SROthat this SI must be performed on all inoperable
NIS channels when they are returned to service.[6]VERIFY that all NIS channel indications
are within+/-3 percent of the determined
core thermal power level.YES o NO o[7]IF a NIS channel was more than 3 percent in error in the non-conservative
direction (core thermal power>NIS), THEN NOTIFY Engineering
to determine if the calibration
error impacts operability
of the NIShigh flux trip.[8]CHECK appropriate
box to indicate whether the following"as-found" acceptance
criteria were satisfied:
ACCEPTANCE
C.RITERIA:
The indicated NIS power level recorded in step[4]is less than or equal to 100.5 percent.YES NO N/A NIS ChannelN-41
0 0 0 NIS Channel N-42 0 0 0 NIS Channel N-43 0 0 0 NIS Channel N-44 0 0 0 RO or SRO
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Page 13 of 33 Unit
6.1 As-Found Data (Continued)
Date-----NOTE Consistency
between the four NIS PR channels is to be considered
when determining
if an adjustment
is desired.[9]IF any channel does not meet acceptance
criteria, OR NIS Channel Adjustment
is desired,THEN
PERFORM adjustment
using section 6.2 AND/OR REDUCE reactor power not to exceed 100 percent.END OF TEXT
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0
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Page 14 of 33 Unit------6.2 NIS Channel Adjustment
Date-----NOTE 1 Performance
of this section is required only for those PR*channels designated
by the Reactor Operator or that did not satisfy the acceptance
criteria in Section 6.1.All other NISchannels
may be marked N/A.NOTE 2 During the performance
of Section 6.2, data required for an inoperable
NIS channel may be marked N/A.[1]IF calculated
average power in Section 6.1 or on printed copy differs by more than 3%from average ReS delta T, THEN NOTIFY Engineering
to determine the cause.[2]VERIFY reactor power has remained constant (+/-0.5%)since performance
of Section1.NOTE The inoperable
channel may be bypassed for up to 4 hours for surveillance
testing of other channels.[3]IF NIS power range channel is inoperable, THEN REQUEST Instrument
Maintenance
to Bypass inoperable
NIS channel in accordance
with 0-PI-IXX-092-001.0.
[4]ENSURE all NIS power range channels are operable or bypassed with no bistables tripped.[5]ENSURE rod control system is in MANUAL in accordance
with 0-SO-85-1.D
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Page 15 of 33 Unit------6.2 NIS Channel Adjustment (Continued)
Date-----NOTE 1 Steps[6]through[9]must be completed on one NIS channel before proceeding
to the next channel.NOTE 2 NIS channels in the following step may be performed outof sequence.[6]IF a rate trip exists (or occurs)on the NIS channel being calibrated, THEN CLEAR that channels trip signal (momentarily
set RATE MODE switch to RESET position)and annunciator
on panel XA-55-6A,"NC-41UorNC-41
K NIS POWER RANGE HlGH NEUTRON FLUX RATE," before proceeding
to the next NIS channel.NIS Channel N-41 NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 Trip Cleared o o o o N/A o o o o First Person-------CV_NOTE The gain potentiometers
have latches which must be disengaged
prior to adjustment, and re-enga*ged
following adjustment.
[7]ADJUST gain potentiometer
on associated
channel's power range B drawer to bring that channel's*
indicated power level to within+/-0.5%of the calorimetric
power recorded in Section 6.1 or as listed on the printed copy.AND ENSURE gain potentiometer
latch re-engaged.
[C.2]Adjustment
Required N/A NIS Channel N-4100 NIS Channel N-4200 NISChannel
N-4300 NIS Channel N-4400 First Person_CV-
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Page 16 of 33 Unit------Date
6.2 NIS.Channel Adjustment (Continued)
[8]IF fine gain potentiometer
on power range B drawer will not provide enough adjustment
to satisfy the calibration
requirements
of step[7], THEN REQUEST Instrument
Maintenance
to adjust the coarse gain (resistor R312, Coarse Level Adjust)inside the applicable
power range drawer, AND N/A o o o o NIS Channel N-41 NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 READJUST fine gain potenti'ometer
to achieve calibration
requirements
specified in step-[7].Adjustment
Required o o o oFirstPersonCV--------,.-
[9], IF additional
NIS channel(s)
require calibration, THEN R*ETURN TO step-[6].[10]WHEN NIS adjustments
have been completed, THEN RECORD"as-left" power level from NIS power range channels.POWER RANGE" AS-LEFT" CHANNEL NIS POWE*R (%)N-41 (XI-92-5005B)
N-42 (XI-92-5006B)
N-43 (XI-92-5007B)
N-44 (XI-92-5008B)
First Person_IV_
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Page 17 of 33 Unit------6.2 NIS Channel Adjustment (Continued)
[11]IF NIS power range channel is inoperable, THEN REQUEST Instrument
Maintenance
to remove Bypass on inoperable
NIS'channel in accordance
with 0-PI-IXX-092-001.0.
[12].CHECK appropriate
box to indicate whether the foHowing"as-left" acceptance
criteria were satisfied.
Date-----ACCEPTANCE
CRIT:ERIA:
The indicated NIS power level recorded in step[10]is within+/-O.5 percent the calorimetric
power level recorded in Section 6.1 or as listed on the printed copy.NIS Channel N-41 NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 YES o o o o NO o o o o RO or SRO N/A o o o o[13]IF accepta.nce
criteria were NOT satisfied for any NIS channel, THEN NOTIFY Shift Manager that acceptance
criteria were NOT met and another performance
of this test is necessary, subsequently
action 2 of LCO 3.3.1.1 (Unit 1)or LCO 3.3.1 (Unit 2)must be satisfied if the other performance
does not meet acceptance
criteria.NOTE NIS channel adjustment
may cause step change in input to rod control.A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.[14]RETURN Rod Control System to AUTO in accordance
with 0-SO-85-1.
END OF TEXT D
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Page 18 of 33 7.0 POST PERFORMANCE
ACTIVITY[1]NOTIFY SRO that test has been completed.
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Page 19 of 33 Unit---Date---NOTE 1 NOTE 2 APPENDIX A Page 1 of 3 CALCULATION
OF CORE THERMAL POWER USING LEFM ICS allows two options for blowdown flows: Option#1 (Preferred)-use point[F2261.A]which requires no operator entered data (computer automatically
updates the blowdown flows)*.Option#2-use manually enteredS/G
blowdown flow rates.Computer point[F2261Alis
more accurate than flow indicators
located in the fan rooms.If the computer point is inoperable
and blowdown flows from the FIS's are used, then indicated core thermal power may be a slightly differentvalue.
[1]ENSURE S/G blowdown flows are updated by performing
the following functions on ICS:[a]SELECT"NSSS AND BOP".[b]SELECT"CALORIMETRIC
FUNCTION MENU".[c]SELECT"UPDATE OPERATOR ENTERED BLOWDOWN FLOW" on menu AND PERFORM one of the following options (N/A option not used): 1.IF using computer point[F2261Al S/G Total Blowdown Flow, T*HEN (a)VERIFY point value is updating (changing values).(b)IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WOo D D D D D
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 20 of 33 Unit---Date---NOTE APPENDIX A Page 2 of 3 Local readings of steam generator blowdown flow are obtained from Panel L-357.2.IF manually updating blowdown flows, THEN[a]RECORD local readings for S/G blowdown flow: RCS SLOWDOWN FLOW LOOP (GPM)1 FI-1-152 2 FI-1-156 3 FI-1-160 4 FI-1-164[b]ENSURE blowdown flows above entered in ICS.[c]IF blowdown flows were updated, THEN WAIT a m*inimum of 10 minutes to allow program to accur.ately
reflect new value.D
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Page 21 of 33 Unit APPENDIX A Date Page 3 of 3 NOTE ICS printout may be used to documentpower
level and NIS values.Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used)and the printed sheet value (if used).SI acceptance
is satisfied in the body of the instruction.
[2]SELECT"DISPLAY CURRENT CALORIMETRIC
DATA" on ICS Calorimetric
menu AND PERFORM one of the following:
[a]RECORD the following:
LEFM Core Thermal Power (U2118)Percent Rated Core Thermal Power (U 1127)OR Mwt---_-----.
0/0-----D[b]PRINT power level and NIS'values AND ATTACH report to this instruction.
D
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Page 22 of 33 Unit---Date-_--:.--NOTE 1 NOTE 2 APPENDIX B Page 1 of 1 SUBSTITUT*ION
OF RCS i\T AT lOW POWER LEVELS40%WITH LEFM NOT AVAILABLE)
RCS delta T loops
are aligned to results of a secondary-side
heat balance.Consequently, using i\Ts to adjust NIS at.Iow power levels still satisfies the requirement
to use heat balance.Loop i\T is used to avoid potentially
non-conservative
errors in NIS power range indication
if adjustments
were made based upon an inaccurate
secondary heat balance at a*low feedwater flowrate.At low power levels the traditional
seco*ndary-side
heat balance (U 1118)is not as accurate as Reactor Coolant LoopT'8.This appendix should NOT be used if LEFM is operable.[1]CALCULATE the average RCSdelta T using control board indications
or computer point for average RCSLoop A (TI-68-2D)
&deg;/0 PLANT COMPUTER Loop B (TI-68-25D)
&deg;/0 OR U0485Loop C (TI-68-44D)
&deg;/0 Loop D
&deg;/0 Total&deg;/0-;-(4)=Avg[2]RECORD average RCS delta T as the core thermal power level 0/0.&deg;/0
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Page 23 of 33 Unit---Date---APPENDIXC Page 1 of 3 CALCULATION
OF CORE-THERMAL POWER LEVEL USING U1118 (>40%WITH LEFM NOT AVAILABLE)
NOTE 1 NOTE 2 NOTE 3 This appendix is used when RCS L1 T is greater than 40%and LEFM (U2118)NOT available, butlCS and U 1118 are available.
ICSallows two options for blowdown flows: Option#1 (Preferred)
-use point[F2261A]which requires no operator entered data (computer automatically
updates the blowdown flows).Option#2-use manually entered S/G blowdown flow rates.Computer point[F2261A]is more accurate than flow indicators
located in the fan rooms.If the computer point is inoperable
and blowdown flows from the FIS's are used in the calculation
of U1118, then expect U1118 to indicate a different value and adjustment
of NIS may be required.[1]ENSURE S/G blowdown flows are updated by performing
the following on les:[a][b]SELECT"NSSS AND BOP".SELECT"CALORIMETRIC
FUNCTION MENU" D D[c]SELECT"UP-DATE OPERATOR ENTERED SLOWDOWN FLOW'on menu AND PERFORM one of the following options (N/A option not used): 1.IF using computer point[F2261A]S/G Total Slowdown Flow, THEN[a]VERIFY point value is updating (changing values).[b]IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WOo D D D
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
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Page 24 of 33 Unit---Date---NOTE APPENDIXC Page 2 of 3 Local readings of steam generator blowdown flow are obtained from Panel L-357.2.IF manually updating blowdown flows, THEN[a]RECORD local readings for S/G blowdown flow: Res BLOWDOWN FLOW LOOP (GPM)1 FI-1-152 2 FI-1-156 3 FI-1-160 4 FI-1-164[b]ENSURE blowdown flows above entered in ICS.[c]IF blowdown flows were updated, THEN WAIT a minimum of 10 minutes to allow program to accurately
reflect new value.D
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Page 25 of 33 Unit---Date---NOTE APPENDIXC Page 3 of 3 ICS-printout may be used to document power level and NIS values.Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used)and the printed sheet value (if used).SI acceptance
is satisfied in the body of the instruction.
[2]SELECT"DISPLAY CURRENT CALORIMETRIC
DATA" on ICS Calorimetric
menu AND D PERFORM one of the following:
[a]RECORD the following:
Venturi Core Thermal Power (U1118)Mwt Percent Rated Core Thermal Power (U1127)0/0 OR[b]PRINT power level and NIS values AND ATTACH report to this instruction.
D[3]IF any value isa blue"NCAl" quality, THEN PERFORM the following:
[a]IF cause of bad data is unknown, THEN REQUEST assistance
from MIG or ICS computer engineer.D[b]INITIATE WO if required.D[c]GO TO Appendix D.D
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Page 26 of 33 Unit---Date---NOTE 1 NOTE 2 APPENDIX D Page 1 of 7 CALCULATION
OF CORE THERMAL POWER LEVEL W.ITH INOPERABLE
PLANT COMPUTER (RCST Greater Than 400/0)This appendix provides guidance determining
calorimetric
power when ICS core thermal power indication (U 1118 and U2118)is unavailable
with power above 40%and the computer cannot be restored in time to complete SR 4.3.1.1.1.
0-PI-SXX-000-022.2
requires several hours from initiation
until completion
of power calculation.
[1]IF O-PI-SXX-000-022.2
will be used for calorimetric
data, THEN PERFORM the following:
[a]NOTIFY Systems Engineering
to perform manual calorimetric
calculation
using
[b]MARK remaining steps"N/A" in this appendix.D D
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Page 27 of33 Unit---Date---NOTE 1 NOTE 2 APPENDIX D Page 2 of 7 The remaining steps determine core thermal power by manually entering calorimetric
data on opposite unit's ICS computer.This method requires adding 3.5%to the calculated
power level for additional
conservatism
due to greater errors associated
with indicator error and readability.
Therefore, power level should be reduced to less than or equal to 96.5%before performance.
Calorimetric
calculation
on opposite unit's ICS assumes that blowdown flow is identical on each unit.This error is accounted for in the 3.50/0 correction
factor.[2]IF opposite unit's ICS will be used to perform a calorimetric
calibration, THEN PERFORM the following:
[a]ENSURE reactor power less than or equal to 96.5%.[b]ENSURE reactor power and RCS temperature
stable.D D
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Page 28 of 33 Unit---Date---NOTE 1 NOTE 2 APPENDIX D Page 3 of 7 If ICSis unavailable, Feed flow and feed temperature
may still be available onLEFM panel[LOCL-500-R183]
in Aux Inst Rm.MFW header temp must be greater than 250&deg;F for reliable LEFM data.[3]IFLEFM feed flow and feed temperature
is available on local LEFM panel, THEN PERFORM the following:
[a]RECORD the following data: Paramete*r
Indication
Reading Loop 1 Feedwater Pressure PI-3-37[M-3]psig Loop 2 Feedwater Pressure
[M-3]psig Lo.op 3 Feedwater Pressure PI-3-92[M-3]psig Loop 4 Feedwater Pressure PI-3-105[M-3]psig Loop 1 S/G Pressure PI-1-2A or 28[M-4]psig Loop 2 S/G Pressure I PI-1-9Aor 9B[M-4]psig Loop 3 S/G Pressure PI-1-20A or 20B[M-4]psig Loop 4 S/GPressure
PI-1-27Aor
278[M-4]psig Total Feedwater Flow LEFM Ibm/hr Feedwater Temperature
LEFM of (must be>250&deg;F)IV[b]SELECT Calorimetric
Main Menu screen on other unit's ICS computer.(step continued on next page)D
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Page 29 of 33 Unit APPENDIX D Date Page 4 of 7[3](Continued)
[c]SELECT LEFMSpecial
Offline Calorimetric
on Calorimetric
Menu.[d]ENTER data in ICS from table in substep 3[a].[e]SELECT function key F3 to execute calculation.
[f]PRINT calorimetric
results.[g]VERIFY data was correctly entered in ICS from table in substep 3[a].[h]RECORD Total S/G Thermal Power from calorimetric
printout: MWt----[i]CALCULATE percent power corresponding
to item[h]IV D D D____MWt==34.55 0/0---NOTE The following step adds 3.5%to calorimetric
power to compensate
for additional
errors in this method.The corrected power value below should be used in Section 6.1.U]CAL*CULATE
corrected core thermal power: (substep[i])%+3.5&deg;lb==[k]VERIFY substeps[g]through U].0/0------IV
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Page 30 of 33 Unit APPENDIX D Date Page 5 of 7 NOTE 1 ,2-PI-ICC-003-036.0
provides details on required test equipment for feedwater temperature
measurement.*
[4]IF LEFM feed flow and feed temperature
is NOT available, THEN PERFORM the fol"lowing:
[a]NOTIFY MIG or Systems Engineering
to install precision temperature
monitoring
'equipment
in feedwater header temperature
wells TW-3-197 an.d TW-3-198[TB el.685].[b]RECORD average feedwater header temperature:
of-----(step continued on next page)D MIG or Eng IV
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Page 31 of 33 Unit APPENDIX D Date Page 6 of 7[4](Continued)
[c]RECORD the following data: Parameter Indication
Reading Loop 1 Feedwater Press PI-3-37[M-3]psig Loop 2 Feedwater Press PI-3-50[M-3]psig Loop 3 Feedwater Press PI-3-92[M-3]psig Loop 4 Feedwater Press PI-3-105[M-3]psig Loop 1 S/G Pressure PI-1-2A or 2B[M-4]psig Loop 2 S/G Pressure PI-1-9A or 9B[M-4]psig Loop 3 S/G Pressure PI-1-20Aor
20B[M-4]psig Loop 4 S/G Pressure PI-1-27A or*27B[M-4]psig Loop 1 Feedwater Flow FI-3-35A or 35B[M-4]Ibm/hr Loop 2 Feedwater Flow FI-3-48A or 48B[M-4]Ibm/hr Loop 3 Feedwater Flow FI-3-90A or 90B[M-4]Ibm/hr Loop 4 Feedwater Flow FI-3-1 03A or 103B[M-4]Ibm/hr IV[d]SELECT Calorimetric
Main Menu screen on other unit's ICS computer.[e]SELECT Special Offline Calorimetric
on Calorimetric
Menu.(step continued on nextpage)D D
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 32 of 33 Unit APPENDIX D Date Page 7 of 7[4](Continued)
[f]ENTER data in ICS"from substeps 4[b]and 4[c].[g]SELECT function key F3 to execute calculation.
[h]PRINT calorimetric
results.[i]VERIFY data from substeps 4[b]and 4[c]was correctly entered in ICS.U]RECORD Total S/G Thermal Power from calorimetric
printout:____MWt[k]CALCULATE percent power corresponding
to item Ul IV o o____MWt==34.55 0/0------NOTE The following step adds 3.5%to calorimetric
power to compensate
for additional
errors in this method.The corrected power value below should be used in Section 6.1.[I]CALCULATE corrected core thermal power: (substep[k])%+3.5%==[m]VERIFY substeps U]through[I].___%IV
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0
CHANNEL CALIBRATION
BY Rev: 18 1&2 HEAT BALANCE COMPARISON
Page 33 of 33 SOURCE NOTES Page 1 of 1 REQUIREMENTS
STATEMENT Ensure calculation
of thermal power is correct before calibrating
excore detectors.
Excore detectors should be calibrated
based on best available power indication.
NIS*power range calibrations
should be performed periodically
following power ascension above 15%power.Careful consideration
and caution should be exercised before adjusting nuclear instrumentation.
Operations
and Engineering
Management
should be notified if larger than normal channel adjustments
are required.0-SI-OPS-092-078.0
will be revised to allow the use of a Plant Computer program to provide an increased frequency of the performan'ce
of thi"s procedure.
SOURCE DOCUMENT INPO SER 89-23 CAQR sao 90052 INPO SER89-09 INPO SOER 90-03 INPO SOER90-03 LER 328/91005 810 910819 844 IMPLEMENTING
STATEMENT C.1 C.2 C.3 C.4 C.5
co
PREPARED/REVISED BY: JPM#46-1 Page 1 of 13 Rev.0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE
MEASURE B.1.g JPM#46-1 SHUTDOWN THE DIESEL GENERATORS
(1A-A&18-8)Date/VALIDATED BY:*APPROVED BY: (Operations
Training Manager)Date/Date/CONCURRED:
**(Operations
Representative)
Date/*Validation
not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual
step changes that do not affect the flow of the JPM.**Operations
Concurrence
required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).
JPM#46-1 Page 2 of 13 Rev.0 NUCLEAR TRAINING REVISION/USAGE
LOG REVISION DESCRIPTION
OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 Initial Issue ALLv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.
JPM#46-1 Page 3 of 13 Rev.0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE
MEASURE Task: Shutdown the Diesel Generators
(1 A-A&18-8)JAiT A task#: 0640060101 (RO)KIA Ratings: 064K1.01 064A2.08 064A3.06 (4..1/4.4)(2.5/2.7)(3.3/3.4)064A1.08 064A2.13
064A4.06 (3.1/3.4)(2.6/2.8)(3.9/3.9)064A2.04 064A3.03 064A4.01 (2.7/3.0)(3.4/3.3)
(4.0/4.3)Task Standard: Diesel Generators
"1 A-A"&"18-8" have been shutdown in accordance
with EA-82-1.Evaluation
Method: Simulator__X__In-Plant--'""--===================================================================================
Performer:
Performance
Rating: SAT Evaluator:
NAME UNSAT SIGNATURE Performance
Time DATE Start Time-,--__Finish Time---==================.=================================================================
COMMENTS
JPM#46-1 Page 4 of 13 Rev.0 SPECIAL INSTRUCTIONS
TO EVALUATOR:
1.Critical steps identified
by an asterisk (*)2.Sequenced steps identified
by an"s" 3.Any UNSAT requires comments 4.Initialize
simulator in IC#191.lf IC-191 not available, reset to IC#5 Trip the reactor, use 1-M-1 handswitchto
emergency start the diesels generators.
Close TDAFW level control valves.5.When directed to perform section 4.2, set BOTH RF EGR11 and EGR12to TEST and THEN BOTH back to NORMAL*to reset the DIG start signal.Set EGR07 and EGR 08 to RESET to reset the 86LOR for the DGs 6.Acknowledge/reset
alarms on all panels.7.This scenario will require a console operator.8.Ensure operator performs the following required actions*for
SELF-CHECKING;
a.Identifies
the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation
Time: CR.20 mins Local....,....--
Tools/Equipment/Procedures
Needed:
, References:
Reference EA-82-1 Title DIGs in Standb Rev No.2
READ.TO OPERATOR Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handoutsheet
I provided you.INITIAL CONDITIONS:
1.The Unit tripped due to an*inadvertent
safety injection.
2.The safety injection has been terminated
and the plant has been stabilized
in MODE 3.3.The Diesel Generators
have been running unloaded for 2 hours and 40 minutes.4.The status file is complete and there are no outstanding
configuration
log entries present for the Diesel Generators.
INITIATING
CUES: 1.You are the Unit 1 CRO and have been directed to shutdown the Unit 1 Diesel Generators
per EA-82-1.2.The 1 A-A DIG is to be shutdown first.3.All Shutdown Boards are energized by offsite power and the SI signal has been reset.4.Informthe SM when 1A and1B DIGs have been shutdown per EA-82-1.
Job Performance
Checklist:
STEP/STANDARD
JPM#46-1 Page 5 of 13 Rev.0 SAT/UNSAT STEP 1.: Obtain appropriate
copy of procedure.
SAT STANDARD: Operator obtains a copy of EA-82-1 and procedes to Section 4.1.COMMENTS: UNSAT Start Time__STEP 2.: 1.SELECT DIG to be shut down:*DIG 1A-A__*DIG 18-8__*DIG 2A-A__*DIG 28-B SAT UNSAT STANDARD: Operator checks 1 A-A and 18-B diesel generators
being selected.COMMENTS: STEP 3.: Cue: 2.IF EA-202-1 was NOT used to unload the selected DIG, THEN DISPATCH AUO to perform Section 4.2 to reset selectedD/G
emergency start signal.Role Playas AVO and accept EA-82-1, Section 4.2.Report that you will report to him when complete.SAT UNSAT Critical Step Booth Operator: Set BOTH RF EGR11 and EGR12 to TEST and THEN BOTH back NORMAL to reset the DIG start signal.Then, setEGR07 and EGR 08 to RESET Cue: After performing
the
Role Playas AVO and report EA-82-1, Section 4.2 complete.STANDARD: Operator dispatches
AUO with EA-82-1, section 4.2.COMMENTS: STEP 4.: 3.GO TO appropriate
section based on table below: SAT rF SELECTED DIG THEN GO to SECTION OlG DIGDIGDIG 1 A-A 18--8 2A-A 2B-B ,.J..l"""t}UNSAT
..Unloaded greaterihaR:
2 Purging: DiG Combustibles.
Section Unloaded tess than 2 hours,&#xa3;nutting C\Q"\vn OlG.o o o o o o o o STANDARD: Operator determines
that section 4.3 is the appropriate
section since the DIG has been running unloaded more than 2 hours.(also checks the 1 A-A and 1 B-B boxes.)COMMENTS:
Job Performance
Checklist:
STEP/ST ANDARD JPM#46-1 Page 60f 13 Rev.0 SAT/UNSAT 1.POSITION selected DIG MODE SELECTOR switch to PARALLEL: The following steps are from section 4.3.NOTE: STEP 5.: DiG'lB-B 28-8 MODE SElECTOR S'wrrCH HS...S2-1'g H3-B2-7a H5-82-1o:08
PARAlLEL*4
D'SAT UNSAT Criti'cal Step STANDARD: Operator places O-HS-82-18, DG 1 A-A MODE SELECTOR, to PARALLEL.COMMENTS: STEP 6.: 2.TURN selected DIG SYNCHRONIZE
switch to SYN: SAT rUG 1A,-A 18-9 2A-A 28-9 SYNCHRONiZE
SWITCH 1-HS--57-47 1-HS-57-14
.2-HS--57-47
2-HS-57-14
t.J UNSAT Critical Step STANDARD: Operator places O-HS-57-47
DG 1 A-A SYNCHRONIZE, to SYN.COMMENTS: STEP 7.: 3.ENSURE selected DIG VOLTAGE REGULATOR switch*inAUTO: SAT DiG 1 A.-A 2A-A.28-B VOLTAGE REGULATOR S'WITCH:H S-8:2-4 2: H
HS-S2:-1:Q.2
PUlL-P-AUTOD: o UNSAT STANDARD: Operator verifies O-HS-82-12, DG 1 A-A VOLTAGE REGULATOR to PULL-P-AUTO.
COMMENTS:
Job Performance
Checklist:
STEP/STAN DARD JPM#46-1 Page 7 of 13 Rev.0 SAT/UNSAT STEP 8.: 4.ADJUST running voltage to match incoming voltage USING DIG VOLTAGE REGULATOR switch: SAT DlG IN:=eOMI1NG
VOLTAGE El-82-e4, El-82-M RUNN:IN:G'VOLTAGE E1-82-5 EI-82-35 EI-82-95;VOL T.AGE M ATC HE 0 4 o UNSAT Critical Step STANDARD: Operator adjusts 0-HS-82-:12, DG 1A-A VOLTAGE REGULATOR, to match voltages on O-EI-82.,.4
and O-EI-82-5.
COMMENTS: STEP 9.: 5.ADJUST selected DIG SPEED CONTROL switch UNTIL associated
synchroscope
rotating slowly in FAST direction:
SAT DlG 18-8:2.A-A 28-8 SPEED CONTROL S)'NCHROSCOPE
SLOV4'lY[IN FAST ,SWITCH
HS-82..*13;<;1-82-1 0;HS-82-43 X!-82-,31 0 UNSAT Critical Step STANDARD: Operator adjust 0-HS-82-13
until synchroscope
O-XI-82-1 is rotating slowly in the fast direction.
COMMENTS: STEP 10.: 6.WHEN synchroscope
needle is at 12 o'clock" position, THEN CLOSE selected DIG output breaker: SAT 016 2A-A 28-B XJ-82-31
DiG OUTPUT BREA;KER'l-H8-57-46A'1-HS-51-'73A
2-HS-57-46A 2-HS-57-73,A.CLOSED*i o o 0, UNSAT Critical Step STANDARD: Operator places 1-HS-57-46A
to the close position when synchroscope
O-XI-82-1is
at the 12 O'clock position resulting in the closing of the DG electrical
breaker as indicated by Red Light LITabovethe breaker handswitch.
COMMENTS:
Job Performance
Checklist:
JPM#46-1 Page 8 of 13 Rev.0 (STEP 11.: STEP/ST ANDARD 7.ADJUST selected DIG SPEED CONTROL switch to raise DIG MW load to 1.6 MW: SAT/U N SAT SAT DIG UNSAT LA-.A.28-8
*3 HS-8-2-43 HS-a2-7:3 Eli-92**'1
OA El-B-2-'1:DOA, o o o o Critical Step ST AND.ARD: Operator intermittently
places O-HS-82-13
to RAISE until the MW loading on O-EI-82-1 OAincreases
to 1.6 mw.COMMENTS: STEP 12.: 8.MAINTAIN+1 MVAR (OUT)for selected DIG, WHILE paralleled
with offsite power: DlG VOLTAGE:D/G REGULATOR
iDlG M:EG.A.VARS
+1 MVAR'1.'SAT UNSAT lA-A 18-8 2B-8 HS-82-12 HS-8242 HS-82-I2&#xa3;:1-82-1 D'l A o o o o Critical Step STANDARD: Operator places O-HS-82-12
to RAISE to establish the MVAR loading on O-EI-82-11A
to+1 MVAR outgoing, then maintains this MVAR loading as the DG is loaded'by intermittently
placing O-HS-82-12
to RAISE.COMMENTS: STEP 13.: Cue: 9.DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG.Role Playas AUO acknowledge
the direction to monitor theD/G 1A-A exhaust stack.SAT UNSAT STANDARD: Operator dispatches
an AUO to the DIG building to monitor DIG 1A-A exhaust.COMMENTS:
Job Performance
Checklist:
STEP/ST ANDARDJPM#46-1 Page 9 of 13 Rev.0 SAT/UNSAT STEP 14.: 10.LOAD selected DIG to 4.0 MW USING its DIG SPEED CONTROL switch WHILE observing the following guidelines:
a.IF stack exhaust smoke becomes twice as dense as normal during loading, THEN STOP DIG loading UNTIL condition clears.b.WHEN exhaust smoke returns to normal, THEN CONTINUE DIG loading.c.DO NOT CONTINUE this procedure UNTIL the following conditions
are met:*DIG load at 4.0 MW AND*Stack exhaust NORMAL.SAT UNSAT Critical Step Cue: When the AUO is asked,*state
the exhaust has cleared up and now appears normal.STANDARD: Operator loads the DIG 1 A-A to 4.0 MW by intermittently
placing82-13 to RAISE until theMW loading on 0-EI-82-10A
increases to 4.0 mw.COMMENTS: STEP 15.: 11.ADJUST selected DIG SPEED CONTROL switch to lower DIG MW load to 0.5 MW: SAT DiG SPEEDCO:NTROL
HS-d2-'13 HS-:E2-43 H5-32-73 o o o UNSAT Crit.ical Step STANDARD: Operator places O-HS-82-13
to LOWER until the MWloading on 0-EI-82-10A
reduces to 0.5 mw.COMMENTS: STEP 16.: 12.ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero: SAT;016 DIG VOLTAGE.Qj'-G MEGAVARS 0'''VAR,!REGULATOR SWITC.H UNSAT lA-A 2A-A 2B-8 H5-82-12 HS-82-42 HS-82-72 HS-S2-1G2
1 A o o D o Critical Step STANDARD: Operator places O-HS-82-12
to LOWER until the MVAR loading on 0-EI-82-11A
reduces to o.COMMENTS:
Job Performance
Checklist:
STEP/STAN DARD JPM#46-1 Page 10 of 13 Rev.0 SAT/UNSAT STEP 17.: 13.PLACE selected DIG output breaker control switch to TRIP: SAT DiG*1B,.;6.2A-A[hfG
:1-iHS-57-46.A.
'1
-13A.2-H3-51-46.A.
2**H3-0:1-13.A.o o o o UNSAT Critical Step STANDARD: Operator places 1-HS-57-46A to the TRIP position.COMMENTS: STEP 18.: 14.GO TO Section 4.4 to shut down DIG.SAT STANDARD: Operator goes to section 4.4 to shut down the DIG 1 A-A.COMMENTS: Evaluator Note: The following steps are from Section 4.4 UNSAT STEP 19.:1.VERIFY selected DIG unloaded with output breaker open: SAT DIG 18-8 2A-A 28-8 DlGOUTPUT BREAKER BREA.KER HAN D SWITCH 1@22 2-HS..*54-45A UNLOADED 8.OUTPUT BREAKER OPEf4D o o o UNSAT STANDARD: Operator verifies DIG 1 A-a output breaker open by green light LIT over Handswitch
1-HS-54-46A.
C'OMMENT'S:
STEP 20.: 2.PLACE selected D/G(s)CONTROL START-STOP
switch to STOP: SAT DiG 18-9 28-8 DIG CO:NTROl START-S*TOP
o o u u UNSAT Critical Step NOTE: Operator may elect to turn the synchroscope
on to verify D/G goes to idle speed when HS is placed to stop.ST*ANDARD:
Operator places handswitch on panel 0-M-26, to the STOP.COMMENTS:
Job Performance
Checklist:
STEP/STANDARD
JPM#46-1 Page 11 of 13 Rev.0 SAT/UNSAT STEP 21.: 3.WHEN selectedD/G(s)
has run at idle speed (400 rpm)for 10 minutes, THEN VERIFY DIG shuts down and speed drops to zero: SAT UNSAT DiG:lA,-A NOTE: Cue: u o 2B-iB Override AN:OVRDN[905]
to OFF to clear the 40 RPM running alarm.When alarm clears, CUE: 10 minutes have elapsed If A-Va notified, play role and state: DIG is now at zero speed.STANDARD: Operator addresses need to monitor this step.They may contact the AUO to have himlher contact the UO when speed is zero.COMMENTS: STEP 22.: 4.ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position: SAT UNSAT OiG:1
:lB-B; 1-H*S-B2:-
1,8:1--HS-82-4:B
o o STANDARD: Operator places handswitch
1-HS-82-18, on
0-M-26, to be in PUSH TO UNIT position.COMMENTS: STEP 23.: 5.ENSURE selected DIG SYNCHRONIZE
switch is in OFF: SAT DlG*2A-A:1-H*S-57-14
2-H*S-57-47
2-HS-57-74
u o o o UN"SAT STANDARD: Operator places handswitch
1-HS-57-47, on panel 0-M-26, in the OFF position.COMMENTS:
J0b Performance
Checklist:
STEP/STANDARD
JPM#46-1 Page 12 of 13 Rev.0 SAT/UNSAT STEP 24.: 6.WHEN selected D/G(s)have cooled, THEN ENSURE ERCW valves to DIG heat exchangers
closed: SAT UNSAT:O/G Critical Step tA.--A LH-B
1-HS.-<67--e=;eA.
1-
2-H,S-=B7--67
A.2-HS-67-e5.A.:0 o=0:0:0 o Cue: Play role of AUO: I will monitor DIG temperature
and ensure DG 1A-A ERCW valves are closed when DIG reaches ambient temp.STANDARD: Operator addresses need to monitor this step.They may contact the AUO to have himlher monitor DIG temperatures
and shut the ERCW valve,1-FCV-67-66, when the DIG is at ambient conditions.-COMMENTS:
STEP 25.: 7.GO TO Section 4.1, step in effect.SAT STANDARD: Operator returns to section 4.1 and determines
the other DG needs to be shutdown.UNSAT Cue: COMMENTS: When candidate returns to section 4.1 to shutdown the*other Diesel Generator, state"We'll stop here." End of JPM Stop Time__
Directions
to Trainee: I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM.I will provide initiating
cues and reports on other actions when directed by you.When you complete the task successfully, the objective for thisjob performance
measure will be satisfied.
Ensure you indicate to me when you understand
your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:
1.The Unit tripped due to an inadvertent
safety injection.
2.The safety injection has been terminated
and the plant has been stabilized
in MODE 3.3.The Diesel Generators
have been running unloaded for 2 hours and 40 minutes.4.The status file is complete and there are no outstanding
configuration
log entries present for the Diesel Generators.
INITIATING
CUES: 1.You are the Unit 1 eRa and have been directed to shutdown the Unit 1 Diesel Generators
per EA-82-1.2.The 1 A-A DIG is to be shutdown first.3.All Shutdown Boards are energized by offsite power and the SI signal has been reset.4.Inform the SM when 1A and1B D/Gshave been shutdown per EA-82-1.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-82-1 PLACING DIGs IN STANDBY Revision 2-QUALITY RELATED Marie-Hankins PREPARED/PROOFREAD
BY:-
RESPONSIBLE
ORGANIZATION:
OPERATIONS
APPROVED BY:
_EFFECTIVE DAT-E: 26 May 03 REVISION DESCRIPTION:
Revised section 4.4 to add steps to place the Mode Selector switch in PUSH IN UNIT position and turn the Sync Switch to OFF.This is an intent change.Added HS UNID for D/G output breakers in section 4.4 step 1.Added a note in section 4.1 to clarify DIG's have not been returned to TS operability
but are place-d ina condition for Auto Restart, if required prior to exiting the EOP's.This is a non-intent
change.
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 page 2 of 16 1.0 PURPOSE To shut down unloaded DIGs and place the DIGs in a standby condition.
If a DIG has been running unloaded greater than 2 hours, thisEAP will load it to purge combustibles
and then unload it and shut it down.2.0 SYMPTOMS AND ENTRY CONDITIONS
2.1 Entry Conditions
A.E-O, Reactor Trip or Safety Injection.
B.E-1, Loss of Reactor or Secondary Coolant.C.E-3, Steam Generator Tube Rupture.D.ECA-2.1, Uncontrolled
Depressurization
of All Steam Generators.
E.ECA-3.1, SGTR and LOCA-Subcooled Recovery.F.ECA-3.2, SGTR and LOCA-Saturated Recovery.G.ECA-3.3, SGTR Without Pressurizer
Pressure Control.H.ES-1.1, 81 Termination.
I.ES-1.2, Post LOCA Cooldown and Depressurization.
3.0 PRECAUTIONS
AND LIMITATIONS
3.1 Precautions
A.If the accountability
siren sounds, the operator should continue performing
this procedure.
The SOS will remain aware of procedure progress and location of performing
personnel.
3.2 Limitations
A.This EAP does NOT meet all procedural
and Technical Specification
requirements
for returning the DIGs to a full standby condition.
This procedure only returns the DIGs to a condition for auto-re*start
to ensure availability
if needed prior to exiting the EOPs.
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 3 of 16 4.0 OPERATOR ACTIONS 4.1 Section Applicability
1.SELECT DIG to be shut down:*DIG 1A-A*DIG 1 B-B*DIG 2A-A*D/G28-8__NOTE If EA-202-1 was used to unload the selected DIG, then the DIG emergency start signal and the shutdown board blackout relays have already been reset.2.IF EA-202-1 was NOT used to unload the selected DIG, THEN DISPATCH AUO to perform Section 4.2 to reset selected DIG emergency start signal.3.GO TO appropriate
section-based on table below: D THEN DIG DIG DIG DIG IF SE-LECTED DIG GO TO SECTION 1A-A 1B-B 2A-A 28-8Unloaded greater than 2 hours, Section 4.3,DDDD Purging DIG Combustibles.
Unloaded less than 2 hours, Section 4.4,DD D D Shutting Down DIG.
SQN EA-82-1 PLACING DIGs IN*STANDBY Rev.2 1,2 Page 4.of 16 4.1 Section Applicability (Continued)
4.IF another DIG to be shut down, THEN GO TO Step 4.1.1 D NOTE This procedure places the DIG's in a condition for Auto-Restart, if required prior to exiting the EOP's.Restoration
to T8 operability
and procedural
requirements
for standby alignment is performed after the EOP's are exited.5.RETURN TO procedure and step in effect.END OF SECTION D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 5 of 16 4.2 Resetting DIG Auto Start Signals NOTE Performance
of Steps 4.2.1 and 4.2.2 are required thefirsttime this section is performed but their performance
is not required on subsequent
passes through this section.1.NOTIFY UO to verify SI reset.2.RESET DIG emergency start signals by performing
the following:
[6.9 KV shutdown board room]a.PLACE all DIG[43T(Ll]switches to TEST: SHUTDOWN BOARD LOGIC SWITCH TEST PANEL1 A-A 43T(L)D 18-8 43T(L)D 2A-A 43T(L)D 28-8 43T(L)D b.VERIFY emergency start signals RESET by observing amber lights lit SHUTDOWN BOARD LOGIC PANEL AMBER LIGHT LIT1 A-A D 18-8 D 2A-A 0 28-8 D D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 6 of 16 4.2 Resetting DIG Auto Start Signals (Continued)
C.PLACE 8.11 DIG[43T(L)]switches to NOR: SHUTDOWN BOARD LOGIC PANEL SWITCH NOR1 A-A 43T(L)D 18-8
D 2A-A 43T(L)D 28-8 43T(L)D 3.PERFORM the following:
a.VERIFY DIG[86 LOR]red lights DARK: DIG RELA Y BOARD RED LIGHT DARK1 A-A D 18-8 D 2A-A D 28-8 D b.PLACE selected DIG[86 LOR]switch to RESET: DIG RELAY BOARD SWITCH RESET1 A-A 86 LOR D 18-8 86 LOR D 2A-A 86 LOR D 28-8 86 LOR D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 7 of 16 4.2 Resetting DIG Auto Start Signals (Continued)
4.GOTO Section 4.1, step in effect.END OF SECTION D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1;2 Page 8 of 16 4.3 Purging DIG Combustibles
CAUTION NOTE Only one diesel shall be operated in parallel with off-site power at any time.This section purges the DIG of any combustibles
accumulated
during the unloaded condition prior to shutting down the DIG.1.POSITION selected DIG MODE SELECTOR switch to PARALLEL: DIG MODE SELECTOR SWITCH PARALLEL1 A-A HS-82-18 D 18-8 HS-82-48 D 2A-A HS-82-78 D 28-8 HS-82-108 D 2.TURN selected DIG SYNCHRON1ZE
switch toSYN: DIG SYNCHRONIZE
SWITCH1 A-A 1-HS-57-47
D 18-8 1-HS-57-74
D 2"A-A 2-HS-57-47
D 2"8-8 2-HS-57-74
D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 9 of 16 4.3 Purging DIG Combustibles (Continued)
3.ENSURE selected DIG VOLTAGE REGULATOR switch in PULL-P-AUTO:
DIG VOLTAGE REGULATOR PULL-P-AUTOSWITCH 1 A-A HS-82-12 D 18-8 HS-82-42 D 2A-A
D 28-8 HS-82-102 D 4.ADJUST running voltage to match incoming voltage USING DIG VOLTAGE REGULATOR switch: DIG INCOMING RUNNING VOL TAGE MATCHEDVOLTAGE VOLTAGE 1 A-A
EI-82-5 D 18-8 EI-82-34 EI-82-35 D 2A-A EI-82-64 EI-82-65 D 2"8-8 EI-82-94" EI-82-95 D 5.ADJUST selected DIG SPEED CONTROL switch UNTIL associated
synchroscope
rotating slowly in FAST direction:
DIG SPEED CONTROL SYNCHROSCOPE
SLOWLY IN FAST SWITCH DIRECTION1 A-A HS-82-13 XI-82-1 D 18-8 HS-82-43 XI-82-31 D 2A-A HS-82-73 XI-82-61 D 28-8 HS-82-103 X"I-82-91 D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 10 of 16 4.3 Purging DIG Combustibles (Continued)
NOTE When closing the DIG output breaker at 12 o'clock position, consideration
should be given to speed of rotation of synchroscope
needle and time it takes to close the breaker.6.WHEN synchroscope
needle is at 12 o'clock" position, THEN CLOSE selected DIG output breaker: DIG SYNCHROSCOPE
DIG OUTPUT CLOSEDBREAKER 1 A-A XI-82-1 1-HS-57-46A D 18-8 XI-82-31 1-HS-57-73A D 2A-A XI-82-61 2-HS-57 D 28...8 XI-82-91 2-HS-57-73A
D 7.ADJUST selected DIG SPEED.CONTROL
switch to raise DIG MW load to 1.6 MW: SPEED CONTROL 1.6 MWDIG SWITCH DIG MEGAWATTS 1 A-A HS-82-13 EI-82-10A D 18-8 HS-82-43 EI-82-40A D 2A-A HS-82-73 EI-82-70A D 28-8 HS-82-103 EI-82-100A
D 8.MAINTAIN+1 MVAR (OUT)for selected D/G,WHILE paralleled
with offsite power: DIG VOLTAGE+1 MVAR" DIG REGULATOR SWITCH DIG MEGAVARS 1 A-A HS-82-12 EI-82-11A D 18-8 HS-82-42
D 2A-A HS-82-72 EI-82-71A D 28-8 HS-82-102 EI-82-101A
D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 11 of 16 4.3 Purging DIG Combustibles (Continued)
9.DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG.D 10.LOAD selected DIG to 4.0 MW USING its DIG SPEED CONTROL switch WHILE observing the following guidelines:
a.IF stack exhaust smoke becomes twice as dense as normal during loading, THEN STOP DIG loading UNTIL condition clears.b.WHENexhaustsmoke
returns to normal, THEN CONTINUE DIG loading.C.DO NOT CONTINUE this procedure UNTIL the following conditions
are met:*DIG load at 4.0 MW AND*Stack exhaust NORMAL.11.ADJUST selected DIG SPEED CONTROL switch to lower DIG MW load to 0.5 MW: DIG SPEED CONTROL SWITCH 0.5 MW1 A-A HS-82-13 D 18-8 HS-82-43 D 2A-A HS-82-73 D 28-8 HS-82-103 D D D D D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 12 of 16 4.3 Purging DIG Combustibles (Continued)
12.ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero: DIG DIG VOLTAGE DIG MEGAVARS o MVAR" REGULATOR SWITCH 1A-A HS-82-12 EI-82-11A D 18-8 HS-82-42 EI-82-41A D 2A-A HS-82-72 EI-82-71A D 28-8 HS-82-102
01A D 13.PLACE selected DIG output breaker control switch to TRIP: DIG DIG OUTPUT BREAKER TRIPPED" 1 A-A 1-HS-57-46A D 18-8 1-HS-57-73A D 2A-A 2-HS-57-46A D 28-8 2-HS-57-73A
D 14.GOTO Section 4.4 to shut down DIG.END OF SECTION D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 13 of 16 4.4 Shutting Down DIG 1.VERIFY selected DIG unloaded with output breaker open: DIG DIG OUTPUT BREAKER UNLOADED&OUTPUT BREAKER HANDSWITCH
BREAKER OPEN1 A-A 1912 1-HS-54-46A
D 18-8 1914 1-HS-57-73A
D 2A-A 1922 2-HS-54-46A
D 28-8 1924 2-HS-57-73A
D 2.PLACE selected D/G(s)CONTROL START-STOP
switch to STOP: DIG DIG CONTROL STOP-V START-STOP SWITCH 1 A-A HS-82-14 D 18-8 HS-82-44 D 2A-A HS-82-74 D 28-8 HS-82-104 D 3.WHEN selected D/G(s)has run at idle speed (400 rpm)for 10 minutes, THEN VERIFY DIG shuts down and speed drops to zero: DIG ZERO RPM-v D 18-8 D 2A-A D 28-8 D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 14 of 16 4.4 Shutting Down DIG (Continued)
4.ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position: DIG MODE SELECTOR SWITCH PUSH IN UNIT1 A-A 1-HS-82-18
D 18-8 1-HS-82-48
D 2A-A 2-HS-82-78
D 28-8 2-HS-82-108
D 5".ENSURE selected DIG SYNCHRONIZE
switch is in OFF: DIG SYNCHRONIZE
SWITCH OFF1 A-A 1-HS-57-47
D 18-8 1-HS-57-74
D 2A-A 2-HS-57-47
D 2B-8 2-HS-57-74
D
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 15 of 16 4.4 Shutting Down DIG (Continued)
6.WHEN selected O/G(s)have cooled, THEN ENSURE ERCW valves to DIG heat exchangers
closed: DIG ERCW TO DIG HEAT EXCHANGERS
CLOSED1 A-A 1-HS-67-66A D 1-HS-67-68A D 1-HS-67-67 A D 1-HS-67-65A D 2A-A 2-HS-67-66A D 2-HS-67-68A D 2B-B 2-HS-67-67 A D 2-HS-67-65A D 7.GO TO Section 4.1, step in effect.END OF TEXT-0
SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 16 of 16 5.0 REFERENCES
None.
}}
}}

Revision as of 17:24, 20 September 2018

Sequoyah Feb Exam 05000327/2008301, & 05000328/2008301 Final Simulator JPMs
ML080720575
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/31/2008
From:
- No Known Affiliation
To:
NRC/RGN-II
References
JPM 57AP2, Rev 3 IR-08-301
Download: ML080720575 (411)
v • d • e


See also: IR 05000327/2008301

Text

.*':,,*'.:,,*,t

..,....".:.,;..:..'.,:",;..

";: ,,:,;.:/,.:

.....,."'.'-,.;.'.'*..**..

,", ,.'....:..."/"

PREPAREDI REVISE'D BY: JPM 57AP2 Page 1 of 10 Rev 3 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE

MEASURE 8.1.a JPM 57-AP2 Respond to High Containment

Pressure, Place RHR Spray in Service Date/VALIDATED BY: APPROVED BY: CONCURRED:

      • (Operations

Training Manager)(Operations

Representative)

Datel Datel Date/*Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual

ste.p changes that do not affect the flow of the JPM.**Operations

Concurrence

re*quired for new JPMs and changes that affect the flow of the JPM(if not driven by a procedure revision).

JPM 57AP2 Page 2 of 10 Rev 3 I NUCLEAR TRAINING REVISION/USAGE

LOG Revision Description

Pages Prepared/Number Of Revision V Date Affected Revised By: 0 Initial issue Y 12/3/01 All L.Pauley Used in 2000 NRC initial exam as 57 AP 1 Revised to latest revision of FR-Z.1 N 8/20/02 4JP Kearney 2 Made back into simulator JPM (was set up to be run in Y 8/4/05 All MG Croteau actual MCR).Set up for current IC and procedure revision.Updated references, wrote and referenced

SCENS file N 10/20105 3,4 JJ Tricoglou 3 Reworded turnover information, referenced

FR-Z.1 rev 4,10 17, revised instructions, added handout sheet, modified standards wording.v-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.-

JPM 57AP2 Page 3 of 10 Rev 3 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE

MEASURE Task: Respond to High Containment

Pressure, Place RHR Spray in Service Note: This JPM satisfies Simulator Manipulation"IN13".JAITA task#: 3110160601

KIA Ratings: 022000 A3.01 (4.1-4.4)026000 GA 13 (3.6-3.6)(RO)022000 A4.04 (3.1-3.20 026000 GAg (3.6-3.6)Task Standard: Attempt to establish one train of RHR spray in service per FR-Z.1.Evaluation

Method: Simulator__X__In-Plant.:..-==========="========================================================================

Performer:

Performance

Rating: SAT Evaluator:

NAME UNSAT SIGNATURE Performance

Time DATE Start Time_Finish Time_===================================================================================

COMMENTS

JPM 57AP2 Page 4 of 10 Rev 3 SPECIAL INSTRUCTIONS

TO EVALUATOR:

1.Sequenced steps identified

by an"s" 2.Any UNSAT requires comments 3.Initialize

simulator in IC#176.If Ie 176 is not available the reset to IC#24 and complete substeps below.a.Activate MF#TH01A at 350/0.b.Activate MFs#CH01 A thru D at 70%(-10.2 psid)c.Complete the actions of ES-1.3, Sump Swapover.Stop RCPs.d.Activate Override ZDIHS6393A

OPEN, to prevent FCV-63-93 from closing.e.Activate Override ZDIHS7241A

CLOSE*, to prevent FCV-72-41 from opening.4.Activate the following, as necessary, to prevent nuisance alarms:*AN:OVRN[96]

to OFF, prevents Turbine Zero Speed alarm**AN:OVRN[214]

to OFF, prevents Saturation

Monitor alarm*AN:OVRN[304]

to OFF, prevents MFP Lo NPSH*AN:OVRN[2155]

to OFF, prevents SG Pressure Lo 5.Insert Remote Function RHR14 ON, places power on FCV-63-1.6.FREEZE the simulator until the operator is ready to commence task.7.Console operator will need to acknowledge

alarms*not associated

with JPM.8.Ensure operator performs the following required actions for SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.8 mins Tools/Equipment/Procedures

Needed: FR-Z.1, step 13 References:

Local-----Reference FR-Z.1 Title Hi h Containment

Pressure Rev No.17===========,===============================================================================

READ TO OPERATOR Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Unit 1 has experienced

a reactor trip and Safety Injection in conjunction

with a large break LOCA.2.The crew has been monitoring

step 13 of FR-Z.1 since FR-Z.1 was implemented.

3.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.INITIATING

CUES: 1.The US directs you to perform FR-Z.1, Step 13 to initiate one train of RHR spray.2.Inform the US when Step 13 has been completed.

Job Performance

Checklist STEP/STANDARD

JPM 57AP2 Page 5 of 10 Rev 3 SAT/UNSAT STEP 1.: Obtain copy of appropriate

procedure.

-SAT Cue: After operator locates FR-Z.1 procedure, provide a copy of-UNSAT FR-Z.1 marked up as appropriate.

Start Time--STANDARD: Operator obtains a copy of FR-Z.1 (begin at Step 13).COMMENTS: STEP 2.:[FR-Z.1, Step 13]MONITOR if RHR Spray should be placed in-SAT service.-UNSAT CHECK Containment

press greater than 9.5 psid.STANDARD: Operator checks PDIS-30-42

through 45 and determines

that pressure is greater than 9.5.COMMENTS: STEP 3.: CHECK at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident.-SAT Cue: IF asked, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident.-UNSAT STANDARD: Operator determines

from initiating

cues (or asks US)that 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed.COMMENTS: STEP 4.: CHECK RHR suction ALIGNED to containment

sump.-SAT Cue: If asked, ES-1.3 has been completed.

-UNSAT STANDARD: Operator check FCV-63-72 and 73 open AND FCV-74-3 and 21 closed.OR asks US if ES-1.3"Transfer to RHR Containment

Sump" has been completed.

COMMENTS:

Job Performance

Checklist STEP/ST AN DARD JPM 57AP2 Page 6 of 10 Rev 3 SAT/UNSAT STEP 5.: CHECK at least one CCP AND one SI pump RUNNING.-SAT STANDARD: Operator ensures at least one CCP is running as indicated by red-UNSAT light on 1-HS-62-1 04A or 1-HS-62-1 08A LIT.AND Ensures at least one SI pump is running as indicated by red lights on 1-HS-63-1 OA or 1-HS-63-15A"LIT".COMMENTS: STEP 6.:[13.b]CHECK

both RHR pumps RUNNING.-SAT STANDARD: Operator checks that both RHR pumps are running as indicated by red-UNSAT lights on

1-HS-20A"LIT".COMMENTS: STEP 7.:[13.c]ESTABLISH Train B RHR spray:-SAT 1.CHECK Train B RHR pump RUNNING.-UNSAT STANDARD: Operator checks that 1 B-B RHR pump is running as indicated by red light on 1-HS-74-20A"LIT".COMMENTS: STEP 8.:[13.c.2)]ENSURE RHR crosstie FCV-74-35 CLOSED.-SAT STAN'DARD:

Operator verifies FCV-74-35 in the CLOSE position as indicated by-UNSAT 1-HS-74-35A

green light ON and red light off.COMMENT.S:

STEP 9.:[13.c.3)]CLOSE RHR Injection FGV-63-94.

-SAT-UNSAT STANDARD: Operator places handswitch

1-HS-63-94A

for RHR injection FCV-63-94 in the CLOSE position.Critical Step COMMENTS:

JobPerformance

Checklist STEP/STANDARD

JPM 57AP2 Page 7 of 10 Rev 3 SAT/UN SAT NOTE: This is the alternate path.-SAT STEP 10.:[13.c.4)]OPEN RHR Spray FCV-72-41.

-UNSAT NOTE: FCV-72-41 will NOT open the operator must go to the RNO and align the A train RHR spray.STANDARD: Operator places handswitch1-HS-72-41A

for RHR injection FCV-72-41 in the OPEN position and recognizes

that the green light stays ON and the red light is OFF, goes to RNO column.COMMENTS: NOTE: The following steps are from FR-Z.1, step 13.c RNO-SAT STEP 11.:[13.c RNO a)]ENSURE RHR Spray FCV-72-41 CLOSED.-UNSAT STANDARD: Operator verifies FCV-72-41 is closed as indicated by green light ON and red light OFF on 1-HS-72-41A.

COMMENTS: STEP 12.:[13.c RNO b)]IF RHR aligned for cold leg recirculation, THEN-SAT ENSURE FCV-63-94 OPEN.-UNSAT STANDARD: Operator places handswitch

1-HS-63-94A

for RHR injection FCV-63-94 in the OPEN position.Critical Step COMMENTS: STEP 13.:[13.c RNO c)]ESTABLISH Train A RHR spray:-SAT (1)ENSURE RHR crosstie

CLOSED.-UNSAT STANDARD: Operator verifies RHR crosstie FCV-74-33 in the CLOSE position as indicated by green light LIT on handswitch

1-HS-74-33A.

COMMENTS:

Job Performance

Checklist STEP/STANDARD

JPM 57AP2 Page 8 of 10 Rev 3 SAT/UNSAT STEP 14.:[13.c RNO c)(2)]CLOSE RHR Injection FCV-63-93.

-SAT-UNSAT STANDARD: Operator places handswitch

1-HS-63-93A

for RHR injection FCV-63-93 in the CLOSE position.Critical COMMENTS: Step STEP 15.: OPEN RHR spray FCV-72-40.

-SAT STANDARD: Operator places handswitch

1-HS-72-40A

for FCV-72-40 in the-UNSAT OPEN position.Critical Step COMMENTS: STEP 16.:[13.d]MONITOR containment

pressure greaterthan

4 psig.-SAT-UNSAT STANDARD: Operator checks PDIS-30-42

through 45 and determines

that pressure is greater 4 psig and continues to the next step.This completes Step 13 and the JPM COMMENTS: STEP 17.: Communicates

with SRO and informs him RHR spray status.-SAT-UNSAT STANDARD: Operator informs SRO that the Train A RHR spray has been placed in service in accordance

with FR-Z.1 and that FCV-72-41 failed to open.Stop Time__COMMENTS: END OF JPM

ECCS Simplified

Drawing*------------1

  • I I I*I*I*I*I*I11: 63-1j:£: i i:._________i FCV-74-24.-£:: FCV:: 74-12:*.*.*.*.: RHR:*.*.I**.I: "------i Fev 63-172 Hot Legs Loops: 1&3 Hot Legs Loops:..._-----_._----_.

__._--------_

.._-_._.._-_.__.._---..__

..-Cold Legs.I1 FCV[j63_22 FCV i FCV.......L--__Charging

...........

[.._...._.*............................................................

__.--_.-_.-..----l**L**'" LCV._11 LCV 62-135..LJ62.136..----1-*----*

Hot Legs*.Loops&3';""...........

v C T FCV 63-156.LCV.r-I62-133 r***

,

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION

OF TASK)DIRECTION TO T*RAINEE: I will explain the initial conditions, a.nd state the task to be performed.

All control room steps shall be performed for this.JPM, including any required communications.

I will provide initiating

cues and reports on other actions when directed by you.Ensure you indicate to me when you understand

your assigned task.To indicate that you have com*pleted

your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Unit 1 has experienced

a reactor trip and Safety Injection in conjunction

with a large break LOCA.2.The crew has been monitoring

step 13 of FR-Z.1 since FR-Z.1 was implemented.

3.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.INITIATING

CUES: 1.The US directs you to performFR-Z.1, Step 13 to initiate one train of RHR spray.2.Inform the US when Step 13 has been completed.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL FUNCTION RESTORATION

PROCEDURE FR-Z.1 HIGH CONTAINMENT

PRESSURE Revision 17 QUALITY RELATED D.A.PORTER PREPARED/PROOFREAD

BY:-----------

RESPONSIBLE

ORGANIZATION:

OPERATIONS

w.T.LEARY APPROVED BY:---------------

EFFECTIVE DATE: 05/31/07 REVISION DESCRIPTION:

Updated ES-1.3 step number reference in Step 5.c RNO.This procedure contains a Handout Page (2 copies).

SQN STEP I HIGH CONTAINMENT

PRESSURE HANDOUT Page 1 of 1 ACTION FR-Z.1 Rev.17 1.4.d RNO 6.10.RNO.12.12.a RNO 12.d 13.MONITOR RWST level greater than 27%.(if any S/G is faulted and air return fans are NOT running)WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment

air return fans running.MONITOR containment

air return fans:*WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment

air return fans running.IF all S/Gs Faulted, THEN CONTROL feed flow at greater than or equal to 25 gpm to each S/G.MONITOR if hydrogen igniters and recombiners

should be turned on: WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN CHECK if hydrogen igniters and recombiners

are required.WHEN ice condenser AHU breakers are open, THEN ENERGIZE hydrogen igniters (if hydrogen concentration

less than 6%).MONITOR if RHR spray should be placed in service:*Containment

pressure greater than 9.5 psig***AND at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since

of accident AND RHR suction ALIGNED to containment

sump AND at least one CCP AND one SI pump RUNNING.13.d.(if RHR spray in service)RNO WHEN Containment

pressure is less than 4 psig, THEN REMOVE RHR spray from service.14.MONITOR if containment

spray should be stopped: (containment

pressure less than 2.0 psig)14.c (if containment

spray suction aligned to sump)RNO WHEN directed by TSC, THEN STOP containment

spray.1a of 16

SQN STEP i HIGH CONTAINMENT

PRESSURE HANDOUT Page 1 of 1 ACTION FR-Z.1 Rev.17 1.4.d RNO 6.10.RNO.12.12.a RNO 12.d 13.MONITOR RWST level greater than 27%.(if any S/G is faulted and air return fans are NOT running)WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment

air return fans running.MONITOR containment

air return fans:*WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment

air return fans running.IF all S/Gs Faulted, THEN CONTROL feed flow at greater than or equal to 25 gpm to each S/G.MONITOR if hydrogen igniters and recombiners

should be turned on: WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN CHECK if hydrogen igniters and recombiners

are required.WHEN ice condenser AHU breakers are open, THEN ENERGIZE hydrogen igniters (if hydrogen concentration

less than 6%).MONITOR if RHR spray should be placed in service:*Containment

pressure greater than 9.5 psig***AND at least 1 hourhaselapsed

since beginning of accident AND RHR suction ALIGNED to containment

sump AND at least one CCP AND one SI pump RUNNING.13.d.(if RHR spray in service)RNO WHEN Containment

pressure is less than 4 psig, THEN REMOVE RHR spray from service.14.MONITOR if containment

spray should be stopped: (containment

pressure less than 2.0 psig)14.c (if containment

spray suction aligned to sump)RNO WHEN directed by TSC, THEN STOP containment

spray.1b of 16

SQN 1.0 PURPOSE HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 This procedure provides actions to respond to a high containment

pressure.2.0 SYMPTOMS AND ENTRY CONDITIONS

2.1 ENTRY CONDITIONS

FR-O Status Trees:*F-O.5, Containment

RED condition:

Containment

pressure greater than or equal to 12.0 psig.*F-O.5, Containment

ORANGE condition:

Containment

pressure less than 12.0 psig AND Containment

pressure greater than or equal to 2.8 psig.3.0 OPERATOR ACTIONS Page 2 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE I I RESPONSE NOT OBTAINED NOTE If this procedure has been entered for an orange path and performance

of ECA-1.1 (Loss of RHR Sump Recirculation)

is required, FR-Z.1 may be performed concurrently

with ECA-1.1.1.2.MONITOR RWST level greater than 27%.VERIFY Phase B valves CLOSED: Panel 6K PHASE B GREEN Panel 6L PHASE B GREEN.IF ES-1.3 has NOT been entered, THEN GO TO ES-1.3, Transfer to RHR Containment

Sump.----..---IF 1-FCV-32-110

(2-FCV-32-111)

&is NOT closed, THEN PERFORM EA-32-3, Isolating Non-Essential

Air to Containment.

IF other valves NOT closed AND flow path is NOT necessary, THEN CLOSE valves.3.ENSURE RCPs STOPPED.Page 3 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 4.DETERMINE if this procedure should be exited: a.CHECK for faulted S/G: a.GO TO Step 5..Any S/G pressure DROPPINGin an uncontrolled

manner OR.Any S/G pressure less than 140 psig.b.CHECK containment

pressure b.GO TO Step 5.less than 12 psig.=--c.CHECK at least one containment

spray pump RUNNING and delivering

flow.d.CHECK at least one containment

air return fan RUNNING.e.RETURN to procedure and step in effect.----.---c.IF containment

pressure is greater than 2.8 psig, THEN GO TO Step 5.d.WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE air return fans RUNNING.Page 4 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 5.VERIFY containment

spray operation:

a.CHECK RHR sump recirculation

capability

AVAILABLE.

b.VERIFY containment

spray pumps RUNNING.c.CHECK RWST level greater than 27%.II RESPONSE NOT OBTAINED a.IF ECA-1.1 , Loss of RHR Sump Recirculation, is IN EFFECT, THEN PERFORM the following:1)OPERATE containment

spray as directed by ECA-1.1.2)GO TO Step 6.b.IF containment

pressure is greaterthan2.8 psig, THEN START containment

spray pumps.c.IF any of following conditions

met:*RWST level less than or equal to 8%OR*containment

sump level greater than 560/0, THEN PERFORM the following:

1)ENSURE cntmt spray pump suction aligned for sump recirc USING ES-1.3, Transfer to RHR Containment

Sump, Step 21.2)GOTO Substep 5.e.(step continued on next page)Page 5 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17.I STEP I I ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 5.d.VERIFY containment

spray suction ALIGNED to RWST:*FCV-72-22 OPEN*FCV-72-21 OPEN.d.ALIGN valves as necessary.

e.VERIFY containment

spray discharge e.OPEN valves for running valves OPEN: containment

spray pumps.*FCV-72-39*FCV-72-2.f.VERIFY containment

spray recirc valves CLOSED:*FCV-72-34*FCV-72-13.

g.VERIFY containment

spray flow greater than 4750 gpm on each train.f.CLOSE valves as necessary.

g.IF NO train of containment

spray is available, THEN PERFORM the following:

1)CONTINUE efforts to restore at least one train of containment

spray.2)NOTIFY TSC to evaluate restoring normal containment

cooling USING EA-30-4, Restoring Containment

Coolers.Page 6 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEP I I ACTION/EXPECTED

RESPONSE 6.MONITOR containment

air return fans:*WHEN at least 10 minutes have elapsed from Phase B, THEN ENSURE containment

air return fans RUNNING.II RESPONSE NOT OBTAINED 7.8.9.VERIFY containment

ventilation

dampers CLOSED: Panel 6K CNTMT VENT GREEN Panel6L CNTMT VENT GREEN.VERIFY Phase A valves CLOSED: Panel 6K PHASE A GREEN Panel6L PHASE A GREEN.VERIFY MSIVs and MSIVbypassvalves

CLOSED.CLOSE dampers.IF flow path NOT necessary, THEN CLOSE valves.CLOSE valves.IF any MSIV CANNOT be closed, THEN CLOSE MSIV locally USING EA-1-1, ClosingMSIVsLocally.

Page 7 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 10.DETERMINE if any S/G Intact: a.CHECK at least one S/G pressure:*CONTROLLED

or RISING AND*Greater than 140 psig.II RESPONSE NOT OBTAINED IF all S/Gs Faulted, THEN PERFORM the following:

1)CONTROL feed flow at greater than or equal to 25 gpm to each S/G.2)OPEN MD AFW pump recirc valves FCV-3-400 and-401 as necessary.

3)GO TO Step 12.CAUTION Isolating all S/Gs will result in a loss of secondary heat sink.11.DETERMINE if any S/G Faulted: a.CHECK S/G pressures:

  • Any S/G pressure DROPPING in an uncontrolled

manner OR*Any S/G pressure less than 140 psig.b.ISOLATE feed flow to affected S/G: MFW*AFW Page 8 of 16 a.GO TO Step 12.

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 12.MONITOR if hydrogen igniters and recombiners

should be turned on: a.DISPATCH personnel to open ice condenser AHU breakers USING EA-201-1, 480 V Board Room Breaker Alignments.

b.CHECK hydrogen concentration

measurement

AVAILABLE:

  • Hydrogen analyzers have been in ANALYZE for at least 5 minutes.c.CHECK containment

hydrogen concentration

less than 6%.d.WHEN ice condenser AHU breakers have been opened, THEN ENERGIZE hydrogen igniters USING Appendix D, Placing Hydrogen Analyzers and Igniters In Service.II RESPONSE NOT OBTAINED b.PERFORM the following:

1)DISPATCH operator to place hydrogen analyzers in service USING Appendix D.(also contained in ES-0.5)2)WHEN hydrogen analyzers have been in ANALYZE for at least 5 minutes, THEN PERFORM substeps 12.c through 12.e.3)GO TO Step 13.=---c.CONSUL T TSC.GO TO Step 13.=---(Step continued on next page.)Page 9 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEP I I ACTION/EXPECTED

RESPONSE 12.e.CHECK containment

hydrogen concentration

less than 0.5%.13.MONITOR if RHR spray should be placed in service: a.CHECK the following:

Containment

pressure greater than 9.5 psig AND At least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident AND RHR suction ALIGNED tocontainmentsump

AND At least one CCP AND one SI pump RUNNING.II RESPONSE NOT OBTAINED e.PLACE hydrogen recombiners

in service USING EA-268-1, Placing Hydrogen Recombiners

in Service.IF hydrogen recombiners

NOT available, THEN CONSULT TSC.a.GO TO Step 14.(Step continued on next page.)'Page 10 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 13.b.CHECK both RHR pumps RUNNING.b.IF only one RHR pump running, THEN PERFORM the following:

1)ENSURE only one CCP RUNNING (same train as running RHR pump preferred).

2)PLACE non-operating

CCP in PULL TO LOCK.3)ENSURE only one SI pump RUNNING (same train as running RHR pump preferred).

4)PLACE non-operating

SI pump in PULL TO LOCK.(Step continued on next page.)Page 11 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 13.c.ESTABLISH Train B RHR spray: 1)CHECK Train B RHR pump RUNNING.2)ENSURE RHR crosstie FCV-74-35 CLOSED.3)CLOSE RHR injection FCV-63-94.

4)OPEN RHR spray FCV-72-41.

II RESPONSE NOT OBTAINED c.IF Train B RHR spray CANNOT be established, THEN PERFORM the following:

a)ENSURE RHR spray FCV-72-41 CLOSED.b)IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-94 OPEN.c)ESTABLISH Train A RHR spray: (1)ENSURE RHR crosstie FCV-74-33 CLOSED.(2)CLOSE RHR injection FCV-63-93.

(3)OPEN RHR spray FCV-72-40.

IF Train A RHR spray.CANNOT be established, THEN PERFORM the following:

a)CLOSE RHR spray FCV-72-40.

b)IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 OPEN.(Step continued on next page.)Page 12 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 13.d.MONITOR containment

pressure greater than 4 psig.II RESPONSE NOT OBTAINED d.WHEN containment

pressure is less than 4 psig, THEN PERFORM the following:

1)ENSURE FCV-72-40 and FCV-72-41 CLOSED.2)IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 and FCV-63-94 OPEN.3)IF ECCS is aligned for hot leg recirculation, THEN ENSURE RHR crosstie valves FCV-74-33 and FCV-74-35 aligned as required by ES-1.4.Page 13 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 14.MONITOR if containment

spray should be stopped: a.CHECK any containment

spray pump RUNNING.b.CHECK containment

pressure less than 2.0 psig.c.CHECK containment

spray suction aligned to RWST.d.RESET Containment

Spray.e.STOP containment

spray pumps and PLACE in A-AUTO.f.CLOSE containment

spray discharge valves:*FCV-72-39, Train A*FCV-72-2, Train B.II RESPONSE NOT OBTAINED a.GO TO Step 15.b.GO TO Step 15.c.NOTIFY TSC to determine when one or both trains of cntmt spray should be stopped.WHEN directed by TSC, THEN PERFORM Substeps 14.d through 14.f.GO TO Step 15.Page 14 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 15.RETURN TO procedure and step in effect.----..---II RESPONSE NOT OBTAINED END Page 15 of 16

SQN HIGH CONTAINMENT

PRESSURE FR-Z.1 Rev.17 Page 1 of 1 APPENDIX D PLACING HYDROGEN ANALYZERS AND IGNITERS IN SERVICE 1.PLACE hydrogen analyzers in service: a.ENSURE the following switches in ANALYZE position:[M-10]*HS-43-200A, Cntmt H2 Analyzer Fan A*HS-43-210A, Cntmt H2 Analyzer Fan B.b.RECORD time:_c.NOTIFY Unit Supervisor

of time that hydrogen analyzers were placed in ANALYZE.D D D D NOTE The following step is performed when directed by an EOP step (after hydrogen concentration

has been verified and ice condenser AHU breakers have been opened).2.WHEN directed to energize hydrogen igniters, THEN ENSURE the following switches in ON position:[M-10]*HS-268-73, H2 Igniters Group A*HS-268-74, H2 Igniters Group B.END OF TEXT Page 16 of 16 D D

PREPAREDI REVISED BY: VALIDATED BY:*APPROVED BY: JPM B.1.b Page 1 of 11 Rev.0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE

MEASURE B.1.b JPM Respond to a#1 Rep Seal Failure Date/Date/Date/(Operations

Training Manager)CONCURRED:

    • Date/(Operations

Representative)

  • Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual

step changes that do not affect the flow of the JPM.**Operations

Concurrence

required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM B.1.b Page 2 of 11 Rev.0 NUCLEAR TRAINING REVISION/USAGE

LOG REVISION DESCRIPTION

OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 New, modifiedfromJPM 403 Y Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.

JPM B.1.b Page 3 of 11 Rev.0 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE

MEASURE Task: Respond to an RCP Seal Failure JAITA task:#0000820501 (RO)KIA Ratings: 003 Reactor Coolant Pump System A2.01 3.5/3.9 Task Standard: 1)Candidate determines

the#1 RCP has a seal malfunction

and enters AOP-R.04 2)Candidate trips reactor, removes the#1 RCP from service, and closes the seal return valve from the pump.Evaluation

Method: Simulator__X__In-Plant_===================================================================================

Performer:

Performance

Rating: SAT NAME UNSAT Performance

Time Start Time_Finish Time_Evaluator:

_/_--

SIGNATURE DATE===================================================================================

COMMENTS

JPM B.1.b Page 4 of 11 Rev.0 SPECIAL INSTRUCTIONS

TO EVALUATOR:

1.Sequenced steps identified

by an"s" 2.Any UNSAT requires comments 3.This task is to be performed using the simulator in IC-10, 14%power ready to roll turbine 4.Put MODE 1 sign on simulator 5.When ready to start, insert malfunction

CV17 A f: 0.60 6.Ensure operator performs the following required actions for SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.14 min Local-----Tools/Equipment/Procedures

Needed: AOP-R.04 References:

1.AOP-R.04 Reference Title Reactor Coolant Pum Malfunctions

Rev No.22=============================================================================

READ TO OPERATOR Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Unit 1 is in MODE 1 at 140/0 reactor power preparing to roll the main turbine.Currently awaiting completion

of maintenance

activities.

INITIATING

CUES: 1.You are the OATC and are to monitor the control board and respond to conditions

as required.This JPM contains Time Critical steps

Job Performance

Checklist STEP/STANDARD

JPM B.1.b Page 5 of 11 Rev.0 SAT/UNSAT STEP 1.: Obtain the appropriate

procedure.

SAT UNSAT STANDARD: Operator identifies

window B-3, FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW lit and uses 1-AR-M5-B to respond.The following 2 steps are from 1-AR-M5-B Window B-3 STEP 2.:[1]Verify High Leakoff condition on affected RCP(s)with the following instruments

Start Time__SAT UNSAT Pump RCP 1 RCP2 RCP3 RCP4 Leakoff Instrumentation

1-FR-62-24

1-FR-62-24

1-FR-62-50

1-FR-62-50

f STANDARD: Candidate determines

that#1 RCP has high Seal flow on 1-FR-62-24

or by looking at the ICS.COMMENTS: STEP 3.:[2]GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.

STANDARD: Candidate enters AOP-R.04 COMMENTS: The following steps are from AOP-R.04 STEP 4.: 1.DIAGNOSE the failure: STANDARD: Candidate determines

Section 2.2 is the appropriate

section and goes to section 2.2 COMMENTS: SAT UNSAT SAT UNSAT

Job Performance

Checklist STEP/STANDARD

JPM B.1.b Page 6 of 11 Rev.0 SAT/UNSAT STEP 5.: 1.MONITOR#1 sealleakoff

less than 6 gpm per pump:-SAT*FR-62-24[RCP1&2]-UNSAT*FR-62-50[RCP3&4]STANDARD: Candidate uses 1-FR-62-24

or by looking at the ICS to determine seal flow on#1 RCP is greater than 6 gpm and goes to the RNO.COMMENTS: STEP 6.: a.MONITOR RCP lower bearing temperature

and seal temperature.

-SAT IF RCP lower bearing temperature

OR seal temperature

are rising-UNSAT uncontrolled, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1][C.2]STANDARD: Candidate uses 1-TI-62-3 and 1-TI-62-4 to determine lower bearing temperature

and seal temperature

are rising and goes to Section 2.1, Reactor Coolant Pump(s)Tripped or Shutdown Required COMMENTS: STEP 7.: 1.CHECK reactor power greater than 10%-SAT-UNSAT STANDARD: Candidate determines

reactor power is greater than 100/0 and continues to the next step.COMMENTS:

Job Performance

Checklist STEP/STAN DARD STEP 8.: 2.TRIP the reactor and GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing

in this procedure.

After candidate completes the immediate actions, state that the SRO and another operator will perform E-O.STANDARD: Candidate trips the reactor by placing reactor trip switch to the trip position.COMMENTS: STEP 9.: 3.STOP and LOCK OUT affected RCP(s).STANDARD: Candidate places handswitch

1-HS-68-8A

to the stop position (critical).

Handswitch

placed in the Pull to Lock position (non-critical).

Record time pump is stopped_COMMENTS: STEP 10.: 4.MONITOR RCP sealleakoff

less than 8 gpm per pump:*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]Evaluator Note: Scale on recorder is 0-10 gpm STANDARD: Candidate determines

that#1 RCP sealleakoff

flow on 1-FR-62-24

is greater than 8 gpm.COMMENTS: JPM B.1.b Page 7 of 11 Rev.0 SAT/UNSAT SAT UNSAT Critical Step SAT UNSAT Critical Step SAT UNSAT

Job Performance

Checklist STEP/STANDARD

STEP 11.: WHEN the RCP has coasted down (30 sec.), THEN CLOSE affected RCP seal return FCV:[C.2]*FCV-62-9[RCP 1]*FCV-62-22[RCP 2]*FCV-62-35[RCP 3]*FCV-62-48[RCP 4]STANDARD: Candidate place 1-HS-62-9 to the Close position within 5 minutes of stopping the RCP Record time FCV is closed_COMMENTS: STEP 12.: 5.PULL TO DEFEAT affected loop 1\T and T-avg:*XS-68-2D (1\T)*XS-68-2M (T-avg)STANDARD: Candidate places 1-XS-68-2D

and 1-XS-68 2M to Loop 1 position and pulls each out.COMMENTS: STEP 13.: 6.CHECK RCPs 1 and 2 RUNNING.STANDARD: Candidate determines

that#1 Reactor coolant pump is not running.COMMENTS: STEP 14.: 6.RNO CLOSE affected loop's pressurizer

spray valve.STANDARD: Candidate verifies Loop 1 PZR Spray Valve 1-PIC68-340D

is closed.May place the controller

to manual.COMMENTS: JPM B.1.b Page 8 of 11 Rev.0 SAT/UNSAT SAT UNSAT Critical Step Time Critical Step SAT UNSAT SAT UNSAT SAT UNSAT

Job Performance

Checklist STEP/STANDARD

STEP 15.: 7.IF RCP Seal T em peratures or Bearing Tem peratures are increasing

uncontrolled

due to loss of Seal Injection, THEN EVALUATE initiating

RCS cooldown.Cue: When step addressed state"Shift Manager is evaluating

the need to cooldown" STANDARD: Candidate addresses the need for the cooldown evaluation.

COMMENTS: STEP 16.: 8.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.Cue: When step addressed state"Shift Manager will evaluate EPIPs" STANDARD: Candidate addresses the step COMMENTS: STEP 17.: 9.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant System-Hot Standby*3.4.1.3, Reactor Coolant System-Shutdown*3.4.6.2, RCS Operational

Leakage Cue: When step addressed state"SRO will evaluate Tech Specs" STANDARD: Candidate notifies SRO to evaluate Tech Spec.COMMENTS: JPM B.1.b Page 9 of 11 Rev.0 SAT/UNSAT SAT UNSAT SAT UNSAT SAT UNSAT

Job Performance

Checklist STEP/STANDARD

STEP 18.: 10.GO TO appropriate

plant procedure.

END OF SECTION Cue: To candidate"'We will stop here" STANDARD: Candidate recognizes

that a transition

from the AOP is required.End of JPM JPM B.1.b Page 10 of 11 Rev.0 SAT/UNSAT SAT UNSAT Stop Time__

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION

OF TASK)Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Unit 1 is in MODE 1 at 14%reactor power preparing to roll the main turbine.Currently awaiting completion

of maintenance

activities.

INITIATING

CUES: 1.You are the OATe and are to monitor the control board and respond to conditions

as required.This JPM contains Time Critical steps

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOI PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES

AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS

Revision 22 QUALITY RELATED PREPARED/PROOFREAD

BY: D.A.PORTER RESPONSI BLE ORGAN IZATION: OPERATIONS

APPROVED BY: W.T.LEARY EFFECTIVE DATE: 12/19/2005

REVISION DESCRIPTION:

Revised to clarify actions if neither RCP lower bearing temperature

nor RCP seal temperature

indication

is available (PER 93845).Corrected inconsistency

between caution in Section 2.0 and Appendix B.

SQN 1.0 PURPOSE REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 This procedure provides the actions necessary to mitigate the effects of a Reactor Coolant Pump (RCP)trip below P-8 (35%power), excessive RCP seal leakage, and various RCP malfunctions.

Page 2 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.0 OPERATOR ACTIONS RESPONSE NOT OBTAINED CAUTION: Exceeding the following limitations

requires trip of the affected RCP, unless RCP operation is required by FR-C.1, Inadequate

Core Cooling or FR-C.2, Degraded Core Cooling:*RCP#1 Seal less than 220 psid*RCP#1 Seal Temperature

greater than 225°F*RCP Lower Bearing Temperature

greater than 225°F*RCP Upper Motor Bearing Temperature

greater than 200°F*RCP Lower Motor Bearing Temperature

greater than 200°F*RCP Motor Voltage less than 5940V or greater than 7260V*RCP Motor Amps greater than 608 amps*RCP Vibration greater than 20 mils on any axis (x and/or y)[C.3]NOTE 1: During plant startup following seal maintenance, the seal package should seat and operate normally following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run time.NOTE 2: RCP trip criteria is also located in Appendix B.This appendix should be referred to throughout

the performance

of this procedure.

1.DIAGNOSE the failure: IF...GOTO SECTION PAGE Reactor Coolant Pump(s)tripped or shutdown required 2.1 4 RCP#1 Seal Leakoff high flow (high flow Alarm)2.2 7 RCP#1 Seal Leakoff low flow (low flow Alarm)2.3 13 RCP#2 Seal Leakoff high flow (high RCP standpipe level)2.4 17 RCP#3 Seal Leakoff high flow (low RCP standpipe level)2.5 20 RCP Motor Stator Temperature

High 2.6 23 Page 3 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is tripped.1.CHECK reactor power greater than 10%.SHUT DOWN to MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.GO TO Step 3.NOTE: This procedure is intended to be performed concurrently

with E-O, Reactor Trip or Safety Injection.

2.TRIP the reactor, and GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing

in this procedure.

___11"---3.STOP and LOCK OUT affected RCP(s).Page 4 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required (cont'd)CAUTION: If the RCP seal return flow control valve (FCV)is NOT closed within 5 minutes of stopping the Rep with excessive leakoff, seal damage may occur.[C.2]4.MONITOR RCP seal leakoff less than 8 gpm per pump:*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]5.PULL TO DEFEAT affected loopT and T-avg:*XS-68-2D*XS-68-2M (T-avg)6.CHECK RCPs 1 and 2 RUNNING.WHEN the RCP has coasted down (30 sec.), THEN CLOSE affected RCP seal return FCV:[C.2]*FCV-62-9[RCP 1]*FCV-62-22[RCP 2]*FCV-62-35[RCP 3]*FCV-62-48[RCP 4]CLOSE affected loop's pressurizer

spray valve.Page 5 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Coolant Pump Tripped or Shutdown Required (cont'd)CAUTION: Restoring seal water injection to a hot seal package could result in failure of the RCP seals.NOTE: The plant should be cooled down to reduce heat input into the pump seal package if RCP seal injection flow has been lost and cannot be restored prior to exceeding temperature

limits.7.IF RCP Seal Temperatures

or Bearing Temperatures

are increasing

uncontrolled

due to loss of Seal Injection, THEN EVALUATE initiating

RCS cooldown.8.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.9.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational

Leakage 10.GO TO appropriate

plant procedure.

___111"---END OF SECTION Page 6 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.2 RCP#1 Seal Leakoff High Flow RESPONSE NOT OBTAINED*CAUTION:*CAUTION: RCP bearing damage may occur if temperature

exceeds 225°F.If the RCP seal return flow control valve is NOT closed within 5 minutes of stopping the RCP with excessive leakoff, seal damage may occur.[C.2]1.MONITOR#1 seal leakoff less than 6 gpm per pump:*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]a.MONITOR RCP lower bearing temperature

and seal temperature.

IF RCP lower bearing temperature

OR seal temperature

are rising uncontrolled, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1][C.2]----=---IF lower bearing temperature

AND seal temperature

indication

are NOT available for affected RCP, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]..(Step continued on next page.)Page 7 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE ,.2.2 RCP#1 Seal Leakoff High Flow (cont'd)1.(Continued)

RESPONSE NOT OBTAINED b.CHECK#1 seal leakoff flow: IF#1 seal leakoff flow greater than 8 gpm, THEN PERFORMthefollowing:

1)INITIATE plant shutdown at 2-5%per minute USING AOP-C.03, Emergency Shutdown.2)WHEN reactor is tripped, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]___;11--..IF#1 sealleakoff

flow less than 8 gpm, THEN PERFORM the following:

1)CONTROL RCP seal injection flow for the affected RCP greater than or equal to 9 gpm.2)CONTACT Engineering

for recommendations

WHILE continuing

with this procedure.(Step continued on next page.)Page 8 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)1.(Continued)

2.MONITOR RCP lower bearing and seal water temperatures

less than 225°F.Page 9 of 34 RESPONSE NOT OBTAINED 3)IMPLEMENT Engineering

recommendations

to address specific RCP seal performance

conditions.

OR COMPLETE normal plant shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> USING appropriate

plant procedure.

4)WHEN reactor is shutdown or tripped, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]--_..IF any of the following conditions

met:*RCP lower bearing temperature

or seal water temperature

greater than 225°F OR*seal leakoff flow greater than 6 gpm AND lower bearing and seal temp NOT available for affected RCP THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)3.MONITOR RCP#1 seal ilP greater than 220 psid:*PDI-62-8A*PDI-62-21A

  • PDI-62-34A
  • PDI-62-47A

4.ENSURE RCP seal water supply flow 6-10 gpm per pump:*FI-62-1A*FI-62-14A*FI-62-27A*FI-62-40A 5.CONTACT Engineering

for recommendations

WHILE continuing

with this procedure.

6.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.RESPONSE NOT OBTAINED GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]___:e---IF seal water supply flow is less than 6 gpm AND CANNOT be restored, THEN ENSURE CCS supply to thermal barriers is less than 105°F:*TR-70-161[CCS HX1A1(2A1)/1A2(2A2)

Outlet Temp]Page 10 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)7.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational

Leakage RESPONSE NOT OBTAINED CAUTION: Slow and uniform temperature

adjustments (approx.50°F in one hour)will prevent thermal shock to the seals.8.CHECK VCT outlet temperature

less than 130°F[TI-62-131].

9.ENSURE VCT pressure between 17 psig and 45 psig[PI-62-122].

ADJUST HIC-62-78A

to reduce VCT temperature

to less than 130°F.Page 11 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.2 RCP#1 Seal Leakoff High Flow (cont'd)10.CHECK RCP lower bearing and seal water temperature

less than 180°F: 11.GO TO appropriate

plant procedure.

.---RESPONSE NOT OBTAINED IF any of the following conditions

met:*affected RCP lower bearing or seal water temperature

greater than 180°F OR*lower bearing and seal water temp indication

NOT available for affected RCP, THEN GO TO Step 1.___;11-.END OF SECTION Page 12 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow 1.CHECK#1 seal leakoff flow greater than 0.8 gpm per pump:*FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]2.CHECK#1 seal leakoff flow greater than 0.9 gpm per pump and NOT decreasing:

  • FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]3.GO TO appropriate

plant procedure.

.---4.ENSURE RCP seal water supply flow between 6 gpm and 10 gpm per pump:*FI-62-1A*FI-62-14A*FI-62-27A*FI-62-40A RESPONSE NOT OBTAINED GO TO Step 4.GO TO Step 4.IF seal water supply flow is less than 6 gpm AND CANNOT be restored, THEN ENSURE CCS supply to thermal barriers is less than 105°F:*TR-70-161[CCS HX 1A1(2A1)/1A2(2A2)

Outlet Temp]Page 13 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow (cont'd)5.CONTACT Engineering

for recommendations

WHILE continuing

with this procedure.

6.ENSURE VCT pressure between 17 psig and 45 psig[PI-62-122].

7.CHECK RCP standpipe level alarms DARK[M-5B, A-2, B-2, C-2, 0-2].RESPONSE NOT OBTAINED MONITOR the following:

a.RCOT parameters (O-L-2 AB, el.669)*Level, LI-77-1*Pressure, PI-77-2*Temperature, TI-77-21 b.Cntmt FI.&Eq.Sump Level rate of rise (ICS pt.U0969)Page 14 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow (cont'd)8.VERIFY RCP#2 seal leakoff less than or equal to 0.5 gpm USING Appendix A, RCDT Level Rate-of-Change.

9.MONITOR RCP lower bearing temperature

and seal water temperature

are stable and within limits (less than 225°F).RESPONSE NOT OBTAINED GO TO Section 2.4, RCP#2 Seal Leakoff High Flow.IF any of the following conditions

met:*affected RCP lower bearing temp or seal water temp rising uncontrolled

OR*affected RCP lower bearing temp or seal water temp greater than 225°F OR*affected RCP lower bearing temp and seal temp indication

NOT available THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]

Page 15 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.3 RCP#1 Seal Leakoff Low Flow (cont'd)RESPONSE NOT OBTAINED CAUTION: NOTE: If low seal leakoff compensatory

actions are NOT successful, seal failure may result as indicated by a sudden increase in seal leakoff flow(greaterthan

8 gpm).Plant shutdown may be terminated

if Seal Leakoff flow stabilizes

at greater than 0.8 gpm with pump Lower Bearing temperature

and Seal Water Temperature

remaining stable (no indications

of seal failure).10.MONITOR RCP#1 sealleakoff

flow greater than 0.8 gpm:*FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]11.CHECK#1 seal leakoff flow greater than 0.9 gpm per pump and NOT decreasing:

  • FR-62-23[RCP 1&2]*FR-62-49[RCP 3&4]INITIATE normal plant shutdown USING appropriate

plant procedures

AND STOP affected RCP within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.IF RCP#1 seal leakoff flow reverts to high leakage (greater than 8.0 gpm):*FR-62-24[RCP 1&2]*FR-62-50[RCP 3&4]THEN GO TO Section 2.1 , RCP Tripped or Shutdown Required...GO TO Step 1...Page 16 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.3 Rep#1 Seal Leakoff Low Flow (cont'd)12.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.13.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational

Leakage 14.GO TO appropriate

plant procedure.

___111._---END OF SECTION Page 17 of 34 RESPONSE NOT OBTAINED

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.4 RCP#2 Seal Leakoff High Flow RESPONSE NOT OBTAINED NOTE: A leakoff of greater than 0.5 gpm indicates that a seal problem exists.1.NOTIFY Engineering

to consult with Westinghouse

for continued RCP operation as necessary.

2.CHECK RCP standpipe level alarm(s)LIT[M-5B, A-2, B-2, C-2, D-2].a.MONITOR RCOT parameters

at Radwaste Panel[Aux Bldg, 669'elev.]:*Level, LI-77-1*Pressure, PI-77-2*Temperature, TI-77-21 b.FILL affected RCP standpipe USING AR-M-5B, Annunciator

Response.*RCP 1[A-2]*RCP 2[B-2]*RCP 3[C-2]*RCP 4[0-2]c.IF RCP standpipe level alarm clears, THEN GO TO Section 2.5, RCP#3 Seal Leakoff High Flow.GO TO Step 3.Page 18 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.4 RCP#2 Seal Leakoff High Flow (cont'd)3.MONITOR RCP#2 seal INTACT:*VERIFY RCP#2 seal leakoff less than or equal to 0.5 gpm USING Appendix A, RCOT Level Rate-of-Change.

response 1-AR-M5-A (window 0-,3)VIBRATION&LOOSE PARTS MONITORING

ALM.*CONTACT Engineering

for recommendations.

RESPONSE NOT OBTAINED PERFORM the following within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s: a.PERFORM normal plant shutdown USING appropriate

plant procedure.

b.WHEN reactor is shutdown or tripped, THEN STOP and LOCK OUT affected RCP.c.PULL TO DEFEAT affected loopT and T-avg:*XS-68-20*XS-68-2M (T-avg)Page 19 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.4 RCP#2 Seal Leakoff High Flow (cont'd)4.CHECK RCPs 1 and 2 RUNNING.5.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.6.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHotStandby

Leakage 7.GO TO appropriate

plant procedure.

--_l1li."'--

RESPONSE NOT OBTAINED CLOSE affected loop's pressurizer

spray valve.END OF SECTION Page 20 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.5 RCP#3 Seal Leakoff High Flow 1.CHECK RCP standpipe level alarms DARK[M-5B, A-2, B-2, C-2, 0-2].RESPONSE NOT OBTAINED PERFORM the following:

a.MONITOR Cntmt FI.&Eq.Sump Level rise rate (ICS pt.U0969)b.FILL affected RCP standpipe USING AR-M-5B, Annunciator

Response:*RCP 1[A-2]*RCP 2[B-2]*RCP 3[C-2]*RCP 4[0-2]c.IF RCP bearing temperature

rising, THEN GO TO Section 2.4, RCP#2 Seal Leakoff High Flow, Step 1.

Page 21 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.5 RCP#3 Seal Leakoff High Flow (cont'd)RESPONSE NOT OBTAINED NOTE: A leakoff rate of greater than 500 cc/hr indicates that a seal problem exists.The frequency and length of time filling the RCP standpipe may indicate the severity of the leak.2.MONITOR RCP#3 seal intact:*VERIFY RCP vibration is within limits of annunciator

response 1-AR-M5-A (window D-3)VIBRATION&LOOSE PARTS MONITORING

ALM.*CONTACT Engineering

for assistance

in determining

acceptable

leak rate for continued RCP operation.

3.CHECK RCPs 1 and 2 RUNNING.4.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.PERFORM the following within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s: a.PERFORM non:nal plant shutdown USING appropriateplantprocedure.

b.WHEN reactor is shutdown or tripped, THEN STOP and LOCK OUT affected RCP.c.PULL TO DEFEAT affected loopT and T-avg:*XS-68-2D*XS-68-2M (T-avg)CLOSE affectedloop'spressurizer

spray valve.Page 22 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.5 Rep#3 Seal Leakoff High Flow (cont'd)5.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, RCS Operational

Leakage 6.GO TO appropriate

plant procedure.

..---END OF SECTION Page 23 of 34 RESPONSE NOT OBTAINED

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.6 RCP Motor Stator Temperature

High RESPONSE NOT OBTAINED CAUTION: Operating the RCP with excess winding temperature

will reduce the expected life of the motor insulation.

NOTE: RCP motor winding temperature

limits are as follows:*329°F if RCS temperature

is less than 540°F.*311°F if RCS temperature

is greater than or equal to 540°F.1.MONITOR RCP Motor Stator temperature

less than applicable

limit by monitoring

the following computer points.:*Pump 1: T0409A, 411A or 412A*Pump 2: T0429A, 431A or 432A*Pump 3: T0449A, 451A or 452A*Pump 4: T0469A, 471A or 472A a.IF RCP Motor Stator temperature

reaches applicable

limit AND indication

is verified valid, THEN PERFORM the following:

1)IF reactor power greater than 10%, THEN INITIATE a plant shutdown at 2%per minute USING AOP-C.03, Emergency Shutdown.2)WHEN reactor power less than 10%, THEN GO TO Section 2.1, RCP Tripped or Shutdown Required.[C.1]

Page 24 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 I STEP I ACTION/EXPECTED

RESPONSE 2.6 Rep Motor Stator Temperature

High (continued)

2.EVALUATE EPIP-1, Emergency Plan Initiating

Conditions

Matrix.3.EVALUATE the following Tech Specs for applicability:

  • 3.2.5, DNB Parameters

-Startup and Power Operation*3.4.1.2, Reactor Coolant SystemHot Standby*3.4.1.3, Reactor Coolant SystemShutdown*3.4.6.2, ReS Operational

Leakage 4.GO TO appropriate

plant procedure.

..---END OF SECTION Page 25 of 34 RESPONSE NOT OBTAINED

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 3.0 SYMPTOMS AND ENTRY CONDITIONS

3.1 Symptoms A.Any of the following annunciators

may indicate a RCP malfunction:

PANEL 0-XA-55-27-B-A, COMPONENT COOLING 0-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW 0-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW 0-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW 0-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 0-XA-55-27-B-E, COMPONENT COOLING/MiSe

0-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW 0-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW 0-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW 0-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 1(2)-XA-55-1B, AUXILIARY POWER/STATION

SERVICE A-1 6900V UNIT BO 1 (2)A TRANSFER A-2 6900V UNIT BO 1 (2)B TRANSFER A-3 6900V UNIT BO 1 (2)C TRANSFER A-4 6900V UNIT BO 1 (2)0 TRANSFER B-1 6900V UNIT BO 1 (2)A FAILURE OR UNOERVOLTAGE

B-2 6900V UNIT BO 1(2)B FAILURE OR UNOERVOLTAGE

B-3 6900V UNIT BO 1 (2)C FAILURE OR UNOERVOL TAGE B-4 6900V UNIT BO 1 (2)0 FAILURE OR UNOERVOL TAGE E-3 MOTOR TRIPOUTPNL1 (2)-M-1 THRU 1 (2)-M-6 Page 26 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 3.1 Symptoms (cont'd)PANEL XA-55-5A, REACTOR COOLANT-STM-FW A-6 TS-68-2M/N

REACTOR COOLANT LOOPS T AVG/AUCT T AVG OEVN HIGH-LOW B-5 CNTMT FLOOR&EQUIP DRAIN SUMP HI-HI-HI B-6 TS-68-2A1B

REACTOR COOLANT LOOPS L1 T OEVN HIGH-LOW 0-3 VIBRATION&LOOSE PARTS MONITOR ALARM PANEL XA-55-5B, evcs SEAL WATER AND RCP A-2 LS-62-6A REAC COOL PMP 1 STANDPIPE LVL HIGH-LOW A-3 FS-62-10 REAC COOL PMPS SEAL LEAKOFF LOW FLOW A-4 PdIS-62-96

SEAL WATER INJECTION FILTER HIGH L1P A-5 LS-68-10AlB

REAC COOL PMP 1 OIL RESERVOIR LEVEL HI-LOW B-2 LS-62-19A REAC COOL PMP 2 STANDPIPE LVL HIGH-LOW B-3 FS-62-11 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW B-4 PdIS-62-97

SEAL WATER INJECTION FILTER 2 HIGH L1P B-5 LS-68-34A1B

REAC COOL PMP 2 OIL RESERVOIR LEVEL HI-LOW C-2 LS-62-32A REAC COOL PMP 3 STANDPIPE LVL HIGH-LOW C-3 FS-62-1 REAC COOL PMPS SEAL WATER FLOW LOW C-5 LS-68-53A1B

REAC COOL PMP 3 OIL RESERVOIR LEVEL HI-LOW 0-2 LS-62-45A REAC COOL PMP 4 STANDPIPE LVL HIGH-LOW 0-3 PdS-62-8 REAC COOL PMPS SHAFT SEAL WATER L1P 0-5 LS-68-76A1B

REAC COOL PMP 4 OIL RESERVOIR LEVEL HI-LOW E-1 REAC COOL PMPS MOTOR STATOR TEMPERATURE

HIGH E-2 TS-62-42 REAC COOL PMPS LOWER BEARING TEMP HIGH E-3 REACTOR COOLANT PUMPS MOTOR THRUST BEARING TEMP HIGH E-4 TS-62-43 REAC COOL PMPS SEAL WATER TEMP HI E-5 FIS-62-12 RCP NO 1 SEAL BYPASS FLOW LOW Page 27 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 3.1 Symptoms (cont'd)PANEL XA-55-6A COMPONENT COOLING A-4 FS-68-6A REACTOR COOLANT LOOP 1 LOW FLOW B-4 FS-68-29A REACTOR COOLANT LOOP 2 LOW FLOW C-4 FS-68-48A REACTOR COOLANT LOOP 3 LOW FLOW 0-4 FS-68-71A REACTOR COOLANT LOOP 4 LOW FLOW E-4 RCP BUS UNDERFREQUENCY

I UNDERVOL TAGE B.Deviations

or unexpected

indication

on any of the following may indicate a RCP malfunction:

1.Erratic or abnormal RCP motor current 2.Erratic RCP motor frequency 3.Erratic or low RCS Loop Flow indications

4.Plant Computer RCP temperature

alarms 5.Indication

of high vibrations

on a RCP 6.Low RCP#1 seal LlP 7.High or low RCP#1 Seal leakoff flow 8.High or low RCP#1 Seal supply flow 9.Increasing

RCP#1 Seal temperature

10.Increasing

RCP lower bearing temperature

11.High VCT temperature

12.High VCT pressure 13.High VCT level 14.Increasing

Reactor Coolant Drain Tank level 15.High Containment

Floor&Equipment Sump Level rate of rise Page 28 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 3.1 Symptoms (cont'd)C.Any of the following automatic actions may indicate a RCP malfunction:

1.RCP trip from motor faults 2.Reactor Trip 3.Safety Injection 3.2 Entry Conditions

None END OF SECTION Page 29 of 34

SQN 4.0 REFERENCES

4.1 Performance

REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 A.EPIP-1, Emergency Plan Initiating

Conditions

Matrix B.E-O, Reactor Trip or Safety Injection C.AR-M-5B, Annunciator

Response 4.2 Technical Specifications

A.3.2.5, DNB Parameters

B.3.4.1.1, Reactor Coolant Loops and Coolant Circulation

-Startup and Power Operation C.3.4.1.2, Reactor Coolant System-Hot Standby D.3.4.1.3, Reactor Coolant System-Shutdown E.3.4.6.2, RCS Operational

Leakage Page 30 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 4.3 Plant Drawings A.47W600, Sheets 57,60 B.47W61 0-68, Sheets 1,2,3,4,6 C.47W61 0-77-3 D.47W61 0-62-2 E.47W61 0-72-1 F.47W61 0-74-1 G.47W61 0-63-1 H.47W61 0-67-1 I.47W61 0-3-3 J.47W61 0-70-1 K.47W61 0-30-2 L.47W61 0-47-1 M.47W61 0-82-1 N.45N765, Sheets 1, 2 O.45N724, Sheets 1, 2, 3, 4 P.45N751, Sheets 1, 2, 3,4, 5, 6, 7, 8 Q.45N732, Sheets 1, 2 4.4 10 CFR A.1 OCFR50, Appendix R Page 31 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

AOP-R.04 Rev.22 APPENOIXA Page 1 of 1 RCOT LEVEL RATE OF CHANGE CALCULATE RCDT level rate of change to obtain RCP#2 seal leakoff flowrate.FINAL VOLUME (gal)-INITIAL

VOLUME (gal)=LEVEL RATE OF CHANGE gpm L1 TIME (minutes)----Figure C.20 Page 1 of 1 REACTOR COOLANT DRAIN TANK LEVEL INDICATION

ON LI-77-1 t-100 Z 1LI 90 (J 0=: 80 LU 0-70..J 60 LLI 50>lIJ 40...I 0 30 LLI 20 J--(5 10-C 0 Z-/l-'V

V....v//'v.....v...,vI.'" l/VV l/i""l/ J'V\vl/l/.....v...... V:;/v l,,'v"\..",'""../'7,,-7-,,/N".'" ru"N.T RJ.NI i(/V"./V""...v....,..v".V./""-JI".../VOLUME*GALLONS 350 300 250 200 150 100 oj lso 10 GAL.INCREMENTS

NOTE: LEVEL TAP NOT AT TANK BOTTOM Page 32 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

APPENDIX B PAGE 1 of 1 RCPTRIPCRITERIA

AOP-R.04 Rev.22 Exceeding the following limitations

requires trip of the affected RCP, unless RCP operation is required by FR-C.1, Inadequate

Core Cooling or FR-C.2, Degraded Core Cooling[C.1]:*RCP#1 Seal less than 220 psid*RCP#1 Seal Temperature

greater than 225°F*RCP Lower Bearing Temperature

greater than 225°F*RCP Upper Motor Bearing Temperature

greater than 200°F*RCP Lower Motor Bearing Temperature

greater than 200°F*RCP Motor Voltage less than 5940V or greater than 7260V*RCP Motor Amps greater than 608 amps*RCP Vibration greater than 20 mils on any axis (x and/or y)[C.3]Page 33 of 34

SQN REACTOR COOLANT PUMP MALFUNCTIONS

COMMITMENT

LIST AOP-R.04 Rev.22 COMMITMENT

ID C.1 C.2 C.3 SUMMARY OF COMMITMENT

Provide clear instructions

to the operators should any seal temperature, pressure, or leakage alarms annunciate.

Include conditions

for continued operation or immediate shutdown.Update procedural

guidance to conform to most recent Westinghouse

recommendations

on RCP shutdown with No.1 seal leakage outside the operating limits.Update procedural

guidance to include RCP vibration as a limitation.

Page 34 of 34 COMMITMENT

CORRESPONDENCE

NER 82-005 INPO SOER 81-007 INPO SOER 82-005 NER 930512001 Westinghouse

Tech Bulletin NSD-TB-93-01-R1

NER 970134001 TROIINPO SER 97-002

PREPAREDI REVISED BY: VALIDATED BY: APPROVED BY:*JPM B.1.c Page 1 of 11 Rev.0 SEQUOY AH NUCLEAR PLANT JOB PERFORMANCE

MEASURE B.1.c JPM WITHDRAW SHUTDOWN BANKS Datel Datel Datel (Operations

Training Manager)CONCURRED:

    • (Operations

Representative)

Datel*Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual

step changes that do not affect the flow of the JPM.**Operations

Concurrence

required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM B.1.c Page 2 of 11 Rev.0 NUCLEAR TRAINING REVISION/USAGE

LOG REVISION DESCRIPTION

OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 Modified JPM Y Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.

JPM B.1.c Page 3 of 11 Rev.0 SEQUOYAH NUCLEAR PLANT ROISRO JOB PERFORMANCE

MEASURE Task: Withdraw Shutdown Banks JAITA task:#0010180101 (RO)Withdraw shutdown Banks KIA Ratings: 001 Control Rod Drive System A3 Ability to monitor automatic operation of the CRDS, including: (CFR: 41.7/45.13)

A3.05 Individual

vs.group rod position 3.5/3.5 Task Standard:1)Initiation

of withdrawal

of shutdown banks is initiated starting with Shutdown Bank A.2)Following failure of the group step counters, the reactor trip breakers are opened in accordance

with Technical Requirement

3.1.3.3.x Evaluation

Method: Simulator----In-Plant_===================================================================================

Performer:

Performance

Rating: SAT NAME UNSAT Performance

Time Start Time_Finish Time_Evaluator:

__-SIGNATURE DATE===================================================================================

COMMENTS

JPM B.1.c Page 4 of 11 Rev.0 SPECIAL INSTRUCTIONS

TO EVALUATOR:1.Sequenced steps identified

by an"s" 2.Any UNSAT requires comments 3.Place MODE 3 sign on the simulator.

4.This task is to be performed using the simulator in IC 183.If not available then raise boron to 1800ppm and withdraw rods to D@216;Trip reactor;Close Reactor trip breakers;Reset FWI and one MFPT, Stop TD AFW pump, and Reset M/D LCVs and stabilize SG levels.Place Rod Control Mode Selector Switch to the Manual position and rest startup switch.5.When the candidate withdraws Shutdown bank A approximately

100 steps, insert I/O Override/RD control rod drive system/Logical Output ZROSCSBAG1 (RESET)to ON to fail the Shutdown Bank A step counters to'0'6.Ensure operator performs the following required actions for SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.16 min Local-----Tools/Equipment/Procedures

Needed: 0-GO-2 0-GO-85-1 TR 3.1.3.3 AOP-C.01 TI-28 References:

Reference Title Rev No, 1.0-GO-2 Unit startup From Hot Standby to Reactor Critical 28 2.0-SO-85-1 Control Rod Drive System 33 3.TR 3.1.3.3 Reactivity

Control Systems, Position Indicating

13 System-Shutdown 4.AOP-C.01 Rod Control System Malfunctions

17 5.T1-28 Curve Book 215=============================================================================

READ TO OPERATOR Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Unit startup in progress following a trip from 100%powerdue to a generator electrical

relay malfunction.

2.Per TI-28, the shutdown banks fully withdrawn positon is 228 steps INITIATING

CUES: 1.You are to withdraw the shutdown banks in accordance

with 0-GO-2, Unit Startup From Hot Standby to Reactor Critical, Section 5.1, Step[26.2]2.Notify the SRO when the shutdown banks are fully withdrawn.

Job Performance

Checklist STEP/STANDARD

JPM B.1.c Page 5 of 11 Rev.0 SAT/U N SAT STEP 1.: Obtain the appropriate

procedure.

SAT UNSAT STANDARD: Operator identifies

0-SO-85-1 and goes to Section 6.3"Manual Operation of Rod Control System Below 15 Percent Power".STEP 2.:[1]ENSURE Section 5.2,Reset/CloseReactor

Trip Breakers has been completed.

STANDARD: Candidate determines

by looking at procedure that section 5.2 is complete.COMMENTS: STEP 3.:[2]IF the shutdown and control rods were withdrawn 5 steps to prevent thermal lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawal.

Cue: If asked"Rods were not withdrawn 5 steps" STANDARD: Candidate N/As the step.COMMENTS: STEP 4.:[3]MOMENTARILY

PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System.STANDARD: Candidate places Rod control Startup Step Counter Reset, 1-SUS, to startup and then releases switch.COMMENTS: Start Time__SAT_UNSAT SAT_UNSAT SAT UNSAT

Job Performance

Checklist STEP/STANDARD

JPM B.1.c Page 6 of 11 Rev.a SAT/UNSAT STEP 5.:[4]ENSURE all Full Length Rod step counters reset to zero.-SAT-UNSAT STANDARD: Candidate verifies all 14stepcounters

are reading'000'COMMENTS: STEP 6.:[5]VERIFY rod control IN-OUT direction lights are NOT LIT.-SAT-UNSAT STANDARD: Candidate verifies that both the RODS IN and the RODS OUT lights are not lit on 1-M-4.COMMENTS: STEP 7.:[6]DEPRESS[RCAS], Rod Urgent Failure Alarm Reset.-SAT-UNSAT STANDARD: Candidate pushes Rod Urgent Failure Alarm Reset, 1-RCAS COMMENTS: STEP 8.:[7]RESET Window 6 (A-6), ROD CONTROL SYSTEM URGENT-SAT FAILURE alarm on panel[XA-55-4B]

using[XS-55-4A], UNSAT Annunciator

RESET/ACKITEST

Switch.-STANDARD: Candidate resets the ROD CONTROL SYSTEM URGENT FAILURE alarm using 1-XS-55-4A

if lit.COMMENTS:

Job Performance

Checklist STEP/STANDARD

JPM 8.1.c Page 7 of 11 Rev.0 SAT/UNSAT[8]VERIFY the following rod control system alarms on panel[XA-55-4B]

are NOT LIT: STEP 9.::WfNOOW NitlMBER NOT LITSAT UNSAT STANDARD: Candidate verifies listed windows on 1-M-4 overhead annunciatot55-48 are not lit COMMENTS: STEP 10.:[9]ENSURE Plant computer points for rod bank position are ZERO using the following computer points: SAT UNSAT o o o o o o o o Cue: After candidate demonstrates

ability to access computer points'All listed points have been verified to be'0'.STANDARD: Candidate verifies listed computer points are reading'0'on ICS.There are several methods/screens

to access the points COMMENTS:

Job Performance

Checklist STEP/STANDARD

JPM B.1.c Page 8 of 11 Rev.0 SAT/UNSAT STEP 11.:[10]MONITOR Control Rod position USING Rod Position Indicators

-SAT ICS screen 30 minute trend during SO&Control Banks UNSAT withdrawal

to aid in detecting rod misalignment.

-STANDARD: Candidate locates the Rod Position Indicator RPI TREND screen on the ICS.(when on RPI screen, the RPI TREND screen can be accessed via clicking on TREND.)COMMENTS: STEP 12.:[11]IF Individual

Rod Position Indication

does not indicate proper rod-SAT position during withdrawal

of SO Banks, THEN UNSAT[a]STOP rod withdrawal.

-[b]ENSURE subcriticality.

[c]CONTACT MIG AND INITIATE troubleshooting.

[d]IF troubleshooting

does not resolve the problem, OR subcriticality

can NOT be verified, THEN INITIATE Reactor TRIP.STANDARD: Candidate acknowledges

the requirement

of the IF/THEN step for individual

RPls.No action required.STEP 13.:[12]IF Individual

Rod Position Indication

does not indicate proper rod-SAT position during withdrawal

of Control Banks, THEN UNSAT GO TO AOP-C.01 section 2.6 Rod Position Indicator (RPI)-Malfunction

-Modes 1 or 2.STANDARD: Candidate acknowledges

the step, realizes it refers to control banks, and No action is required for this task of withdrawing

shutdown banks COMMENTS:

Job Performance

Checklist STEP/ST AN DARD JPM B.1.c Page 9 of 11 Rev.0 SAT/UNSAT STEP 14.:[13]PLACE[HS-85-5110], Rod Control Mode Selector to the SBA-SAT position.UNSAT-STANDARD: Candidate rotates Mode Control Mode Selector, 1-HS-85-511

0, counterclockwise

to the SBA position Critical Step COMMENTS: STEP 15.:[14]VERIFY Rod Speed Indicator[51-412], indicates-SAT 64 Steps/minute.

UNSAT-STANDARD: Candidate determines

SI-412, Rod Speed, on 1-M-4 vertical panel is reading 64 steps/min COMMENTS: STEP 16.:[15]ENSURE Shutdown Bank A demand position counters-SAT operational

by performing

the following:

[C.2]UNSAT[a]BUMP[HS-85-5111], Rod Control Switch to withdraw-Shutdown Bank A one-half step at a time, for one full step.[b]CHECK group demand position counters advance properly.[c]BUMP[HS-85-5111]

to withdraw Shutdown Bank A one-half step at a time, for the second full step.[d]VERIFY group demand position counters advance properly.[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

B.INITIATE WO to have counter repaired.C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank A fully INSERTED.2.RETURN to beginning of this step.STANDARD: Candidate uses Rod Control, 1-HS-85-5111, IN-OUT switch to withdraw SBA rods 2 steps in 12 step increments

while checking the group step counters are operating properly.COMMENTS:

Job Performance

Checklist STEP/STANDARD

Note to evaluator:

The shutdown bank full out position is stated in the initial conditions, if candidate refers to TI-28 provide a cue that the full out position is 228 steps.STEP 17.:[16]WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN position using[HS-8S-S111].

Cue: If candidate initiates use of TI-28 to determine full out position, state"The full out position is 228 steps." STANDARD: Candidate uses Rod Control, 1-HS-85-5111, IN-OUT switch on 1-M-4 to withdraw SBA COMMENTS: Note to evaluator:

Malfunction

to fail step counters is to be inserted when the rods reach approximately

100 steps.Candidate may refer to TR-3.1.3.3.

If so the required action is to open the Reactor Trip breakers.STEP 18.: Open the Reactor Trip Breakers Cue: After the reactor trip breakers have been opened state'We will stop here" STANDARD: Candidate determines

the Group 1 step counter is not capable of determining

the demand position for each of the Shutdown bank a rods within2 steps and opens the reactor trip breakers.COMMENTS: JPM B.1.c Page 10 of 11 Rev.0 SAT/UNSAT SAT UNSAT Critical Step SAT UNSAT Critical Step Stop Time__

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION

OF TASK)DIRECTIONTOTRAINEE:

I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating

cues and reports on other actions when directed by you.Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Unit startup in progress following a trip from 1000/0 power due to a generator electrical

relay malfunction.

2.Per TI-28, the shutdown banks fully withdrawn positon is 228 steps INITIATING

CUES: 1.You are to withdraw the shutdown banks in accordance

with 0-GO-2, Unit Startup From Hot Standby to Reactor Critical, Section 5.1, Step[26.2]2.Notify the SRO when the shutdown banks are fully withdrawn.

Sequoyah Nuclear Plant Unit 0 General Operating Instructions

O-GO-2 UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL Revision 0028 Quality Related Level of Use: Conti"nuous

Use Effective Date: 10-31-2007

Responsible

Organization:

OPS, Operations

Prepared By: D.A.Porter Approved By: W.T.Leary Current Revision Description

Revised Section 5.1 steps[28]and[29]to clarify applicability

of Sect.5.2 and 5.3.Added Sect.5.2 step[67].Modified title of Sect.5.2 and 5.3.Added limitation

associated

with minimum temp for criticality.

Provided more specific guidance on S/G level control in Sect.4.0 Step[7].THIS PROCEDURE IMPACTS REACTIVITY

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 2 of 85 Table of Contents 1.0 FI*RST SECT.ION 3 1.*1 Purpose: 3 1.2 Scope 3 2.0 REFERENCES

3 2.1 Performance

References

3 2.2 Developmental

References

5 3.0 PRECAUTIONS

AND LIMITATIONS

...........................................*...............................

6 3.1 PRECAUTIONS

6 3.2 LIMITATIONS

8 4.0 PREREQUiSiTES

......................*..........................9 5.0 INSTRUCTIONS

12 5.1 Actions to be performed prior to a reactor startup 12 5.2 Reactor Startup with Low Power Physics Testing 21 5.3 Reactor Startup without Physics Testing 45 6.0 RECORDS 69 A*ppendix A: DELETED70 Appendix B: MODE 3 TO MODE 2, 1 REVIEW AND APPROVAL 71 Appendix C: DETERMINING

SOURCE RANGE COUNT RATE DOUBLING 79 Appendix D: ACTIONS IF REACTOR STARTUP MUST BE ABORTED 80, Appendix E: ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY

81 Source Notes 83 ATTACHMENTS

Attachment

1: UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 70f 85 3.1 PRECAUTIONS (continued)

2.During Rod Movement a.Ensure RO has peer check b.EnsureRO is following procedure c.EnsureRO understands

criteria for stopping rod motion (based upon number of steps and/or nuclear instrument

response)d.Watch performance*

of rod manipulation

while listening to audible indication

of rod.step e.Ensure peer checking meets expectations (OPDP-1)f.Re-verifyitems

of initial evaluation (on previous page)g.Monitor plant for expected response

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 8of8S 3.2 LIMITATIONS

A.Simultaneous

reactivity

addition by rod withdrawal

and dilution is NOT allowed while in the source range.B.If at any point during the approach to criticality, ONE of the two source range detectors shows an unexplained

increase in count rate equal to or greater than a factor of 5, or if BOTH source range detectors show an unexplained

increase in count rate equal to or greater than a factor of 2, the approach to criticality

shall be SUSPEN*DED

IMMEDIATELY (Le., all rod withdrawals

and/or boron dilutions shall be terminated).

Further positive reactivity

changes shall not be resumed until an evaluation

is performed and the Shift Manager authorizes

a resumption

in the approach to criticality.

C.After refueling operations, the NIS indications

may be inaccurate

until calibration

at higher power levels.The NIS calibration

procedures

will adjust the PRM trip set points to ensure that the excore detectors do not contribute

to an overpower condition.

Prior to startup, the PRM high range flux trip setpoint will be adjusted from 109 to 60%, with the rod stop (C-2)remaining at 103%.[C.3]D.While in Mode 3, maintain the Reactor Coolant System boron concentration

in accordance

with 0-SI-NUC-000-038.0, Shutdown Margin requirements.

E.The stepping or tripping of the.Control Rod during periods when coolant crud level are high should be kept to a minimum.This will limit the possibility

of CRDMmis-stepping

due to crud contamination

of CRDM latch assemblies.

F.The lowest operating loop temperature (T-avg)shall be greater than or equal to 541°F (LCO 3.1.1.4, Minimum Temperature

for Criticality).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 9 of 85 4.0 STARTUP No.---PREREQUISITES

Unit---NOTES1)Throughout

this Instruction

where an IFITHEN statement exists, the step should be N/A'd if the condition does not exist.2)Prerequisites

may be completed in any order.3)Management

oversight is required for a Reactor Startup after a non-refueling

outage.A Reactor Startup after a refueling outage is a CIPTE.[1]ENSURE Instruction

to be used is the latest copy of effective version.t v 1A[2]REVIEW Precautions

and Limitations.

[3]INDICATE below which instruction

this GO is being entered from:*0-GO-1 (cold shutdown to hot standby)*0-GO-6 (30%reactor power to hot standby)*0-GO-7 (hot standby to cold shutdown)*0-GO-5 (normal power operation)

[4]MAINTAIN pressurizer

pressure within the normal operating band by use of the pressurizer

heaters and spray valves.o o o[5]MAINTAIN pressurizer

level greater than or equal to 25%.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 10 of8S 4.0 STARTUP No.---PREREQUISITES (continued)

Unit-i-NOTE Due to instru*ment

inaccuracies

the steam dump or SG atmospheric

relief valve setpoint of 84%or 1005 psig maybe+/-1%or+/-12 psig off.[6]MAINTAIN T AVG stable at approximately

547°F with steam dumps in pressure mode or with SG atmospheric

relief valves.NOTE Minor S/G level variations

which exceed the plus or minus 7%band should not be considered

a procedural

violation.

[7][8][9]MAINTAIN steady-state

S/G levels at approximately

33%(plus or minus 7%)using Auxiliary Feedwater.

ENSURE all reactor coolant pumps are in operation in accordance

with 1,2-S0-68-2, Reactor Coolant Pumps.[C.12]IF the reactor vessel head has been removed, THEN ENSURE conditional

performance

of 0-SI-SXX-085-043.0, Rod Drop Time Measurements, has been performed to comply with SR 4.1.3.4.a.

[10]REQUEST Periodic Test Coordinate

to confirm that the following checklists

have been distributed:

.[10.1]Mode 3 to Mode 2, 1, Surveillance

Checklist (NA if previously

performed for this startup).[10.2]Reactor Trip Breaker Checklist (NA if previously

performed for this startup).[11]ENSURE East Valve Vault Room Vent Chute dampers OPEN.(inside door near SPING Room, Ref.PER 03-002446-000).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 11 of 85

4.0 STARTUP No.---PREREQUISITES

.(continued)

[12]NOTIFY MIGto

LR-3-43A and LR-3-98A, Steam Generator Wide Range Level Recorders, to 80 0/0-90 0/0.[13]E*NSURE each performer documents their name and initials: Date L!l

I Print Name Initials Print Name InitialsAbbot fA°Jk\L 6..!END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 12 of 85 5.0 STARTUP No.---INSTRUCTIONS

Unit

5.1 Actions to be performed prior to a reactor startup[1]ENSURE Section 4.0, Prerequisites

complete.WItt NOTE Steps 5.1[2]through 5.1[11]may be performed in any order.[2]INTIATE Appendix B, , Mode 3 to Mode 2,1 Review And Approval while continuing

with this instruction.

[3]OBTAIN assistance

from Systems Engineering

to complete Appendix B steps associated

with Pressurizer

Spray line bypass valves.NOTE Steps for MFPT startup maybe performed in parallel with other activities.

The MFPT trip busses shall be energized prior to entering Mod'e 2 (LeO 3.3.2.1 or 3.3.2)except as allowed by LCO 3.0.4.[C.1][4]INITIATE applicable

section(s)

of 1, 2-S0-2/3-1

to prepare at least one MFP for startup, while continuing

with this instruction.(N/Aif no MFPT available)

[5]ENSURE TDAFW LCVs are in NORMAL.y/1A 1st

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 13 of 85 STARTUP No.Unit+-Date 5.1 Actions to be performed prior to a reactor startup (continued)

CAUTION Rapid changes in pressurizer

enclosure temperature

may result in pressurizer

safety valve simmer.[6]IF lower compartment

coolers are not in service, THEN[6.1][6.2]ALIGN lower compartment

coolers to maintain pressurizer

enclosure temperature

less than 11 oaF in accordance

withO-SO-30-5.

MONITOR Pressurizer

enclosure temperature

using Plant Computer pt.T1001A.[7]IF control roddrivecoolers

are not in service, THEN[7.1][7.2]ALIGN control rod drive coolers to maintain shroud enclosure temperature

less than 164°F in accordance

with 0-SO-30-6.

MONITOR Reactor Cavity Air temperature

using Plant Computer pt.T1014A.NOTE New analysis is not required for this startup.Routine analysis is sufficient

unless there is reason to suspect che.mistry

has been changed.[8]NOTIFY Chemistry Supervisor

that mode change from 3 to 2 requires sampling in accordance

with O-SI-CEM-OOO-050.0,

.2, and O-SI-CEM-030-415.0

requirements.

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 14 of 85 5.1 STARTUP No.Unit 4-

to be performed prior to a reactor startup (continued)

Date 0 llxI I NOTE To preserve the life of 20 AST and 20*ET, power must be removed from turbine trip bus A and trip bus B if unit startup is extended.[9]ENERGIZE main turbine trip buses by CLOSING the following breakers (NA breakers not applicable):

UNIT TRAIN BREAKER 250V DC POSITION INITIALS WIll TRAINA 1-BKRD-47-KA/516 BATT Bd 1 CLOSED 1st 1TRAINB 1-BKRD-47-KB/516 BATT Bd 2 CLOSED 1 st lJ/l{)TRAIN A 2-BKRD-47-KA/519 BATT Bd 1 CLOSED 1st 2 i,vf If TRAIN B 2-BKRD-47-KB/519

BATT Bd 2 CLOSED 1st NOTE Step 5.1[10]may be marked N/A if not required.[10]PERFORM 0-PI-OPS-047-723.0, 20IAST, 201ET, 20-110PC, and 20-210PC Operability

Verification (N/A if not performed).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 15 of 85 5.1 Actions to be performed prior to a reactor startup (continued)

STARTUP No.---Unit 1 CAUTION Operation of the EHCpumps without the turbine being reset will result in overheating

of the EHC fluid and"pumps.NOTE Startup of EHC and turbine reset"may be postponed until later in startup.(N/Aif postponed)

oj/if-LuiII Date[11][12][13]ENSURE EHC system in service in accordance

with 1,2-80-47-2 (NA if previously

performed).

IFno MFPT is ready for start up per 1,2-80-2/3-1, THEN GO TO Section 5.1[18].ENSURE MFPT designated

for startup has been tested and ready for start up per 1, 2-80-2/3-1

PRIOR to proceeding

with the next step.U/1{)Initials

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 16 of 85 STARTUP No.Unit--1-Date

5.1 Actions to be performed prior to a reactor startup (continued)

NOTES 1)Steps for MFPT startup may be performed in parallel with other activities.

The MFPT trip busses shall be energized prior to entering Mode 2 (LCO 3.3.2.1 or 3.3.2)except as allowed by LeO 3.0.4.[C.1]2)Power is placed on only ONE MFPT trip bus in Step 5.1[14]to prevent inadvertent

AFWP start.[14]ENSURE power restored to ONLY ONE of MFPT tri.p busses on the applicable

unit: (N/A breakers not applicable.)

[C.1]ELECTRICAL

BREAKER INITIALS PUMP BREAKER NO.BOARD POSITION 250v DC MFPT 1A 1-BKRD-46-KA/523

Battery Bd I CLOSED 1st CV 250v DC 0'iA-MFPT 18 1-BKRD-46-KA/524

Battery Bd I CLOSED 1st 250v DC MFPT 2A 2-BKRD-46-KB/523

Battery Bd 2 CLOSED 1st CV 250v DC MFPT 28 2-BKRD-46-KB/524

Battery Bd 2 CLOSED 1st CV

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 I TO REACTOR CRITICAL Rev.0028 Page 17 of 85 STARTUP No.Unit--l-Date 5.1 Actions to be performed prior to a reactor startup (continued)

CAUTION Failure to reset a MFPT prior to energizing

the remai"ning

MFPT trip buss will initiate an ESF actuation.

NOTE If 81 signal or Hi/Hi steam generator level has occurred, Reactor Trip Breakers will have to be cycled.[15]RESET MFPT energized in step 5.1[14]above.vV1A 1st o&4f tJ

Time ate 0041 6\/j{/oJ Time Date NOTE IF the remaining NON-running

MFPT is not available, THENN/A step 5.1[16]and 5.1[17][16]RESTORE power to remaining MFPT Trip Bus on applicable

unit.(N/A breakers not applicable)

PUMP BREAKER NO.ELECTRICAL

BREAKER INITIALS BOARD POSITI"ON 250v DC Battery MFPT 1A 1-BKRD-"46-KA/523

Bd I CLOSED 18t CV 250v"DC Battery MFPT 1B 1-BKRD-46-KA/524

Bdl CLOSED 1st CV 250v DC Battery MFPT 2A 2-BKRD-46-KB/523

Bd 2 CLOSED 1st CV 250v DC Battery MFPT 28 2-BKRD-46-KB/524

Bd 2 CLOSED 1st CV

SQN UNIT STARTUP FROM.HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 18 of 85 5.1 STARTUP No.

Actions to be performed prior to a reactor startup (continued)

[17]RESET MFPT energized in step 5.1[16]above.1 st CV Time Time Date Date[18]SELECT one source range channel and one intermediate

range channel with the highest readings to record on NR 45.[19]ENSURE audio count rate channel isin operation and selected for source range channel with highest reading.[C.11][20]ENSURE all reactor first out alarms reset.NOTE Refer to 1-PI-OPS-000-021.1 (Unit 1)or 2-PI-OPS-000-023.1 (Unit 2)for updating the Plant Computer.[21]IF ICS is available, THEN ENSURE Plant Computer is reset and updating (NA if previously

performed).

[C.S]NOTE Closing of the RTB's for performance

of O-SI-OPS-085-011.0 (SR4.1.3.3)

is addressed in Licensing and NRC TelephoneNisit

Report RIMs#S10 960521 800.[22]IF

is out-of-frequency, THEN[22.1]CLOSE RTB's provided Group Demand counters have no known deficiencies.

[22.2]PERFORM 0-SI-OPS-085-011.0 (NA if above step cannot be performed).

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 19 of 85 STARTUP No.Unit-L Date5.1 Actions to be performed prior to a reactor startup (continued)

[23]IF control rods were withdrawn 5 steps to prevent thermal lockup during ReS heatup, THEN INSERT control rods in accordance

with 0-SO-85-1.

[24]ENSURE Rod Bank Update completed by performing

the following:

[24.1]DEPRESS NSSS and BOP button on ICS main screen.if[24.2]DEPRESS-ROD BANK UPDATE Button AND ENSURE all bank positions are zero.GV'[24.3]DEPRESS F3 to save these rod bank positions.

UV NOTE TI-28 defines fully withdrawn position.[26]IF shutdown rods are inserted, THEN PERFORM the following:

[26.1]VERIFY sufficient

shutdown reactivity

exists USING 0-SI-NUC-000-038.0, Shutdown Margin.[26.2]WITHDRAW Shutdown Rods to fully withdrawn position in accordance

with 0-SO-85-1.

1st CV

SQN UNIT STARTUP FROM HO'T STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 20 of 85 STARTUP No.Unit Date5.1 Actions to be performed prior to a reactor startup (continued)

[27]CONDUCT a pre-evolution

briefing, stressing the following points:*Management

Expectations

  • Limitations/Precautions
  • Avoid activities

which distract the operators[SQ990136PERJ

  • Appropriate

Contingencies

  • Communications
  • Chain of Command*Requirements

for conservative

actions and strict compliance

with written procedures

when repositioning

control rods.[C.11]SRO[28]IF this start up is after a refueling outage AND Low Power Physics Testing has NOT been performed, THEN[28.1]VERIFY applicable

actions in Section 5.1 completed or initiated.

[28.2]GO TO Section 5.2.[29]IF this start up is after a non-refueling

outage OR Low Power Physics Testing has already been completed, THEN[29.1]VERIFY applicable

actions in Section 5.1 completed or initiated.

[29.2]GO TO Section 5.3.[30]IF unit is to be shutdown, THEN GO TO 0-GO-7, Unit Shutdown from Hot Standby to Cold shutdown.END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 21 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing[1]VERIFY applicable

actions in Section 5.1 completed or initiated.

Date---NOTE Steps 5.2[2]through 5.2[9]may be performed out of sequence.[2]IF anyMFPT trip buss is NOT energized, THEN[2.1]ENSURE requirements

of LCO 3.0.4 are satisfied.

[2.2]NOTIFY UnitSRO that LCO 3.3.2.1 (3.3.2)action 20 will apply when Mode 2 is entered.[3]ENSURE Appendix B, Mode 3 to Mode 2, 1 Review and Approval has been completed to ensure all restraints

to Mode 2, 1 entry have been resolved and approvals for mode change granted.[4]BLOCK the Source Range High Flux At Shutdown alarm:[4.1]PLACE both HI FLUX AT SHUTDOWN switches on panel M-13 to BLOCK position.[4.2]VERIFY annunciator

XA-55-4B, window C-1, SOURCE RANGE HIGH SHUTDOWN FLUX ALARM is LIT.[C.2]BLOCK SM o[5]VERIFY greater than or equal to 0.5 cps on highest reading SR instrument.

o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 22 of 85 STARTUP No.Unit Date----5.2 Reactor Startup with Low Power Physics Testing (continued)

NOTE The following count rates may be used as a reference during the approach to criticality.

[6]RECORD SR count rates from two of the following:

[C.2](NIA instruments

not used) (N31)cps XI-92-5002A (N32)cps OR XI-92-5001

B XI-92-5002B (N31)(N32)CAUTION___cps___cps Date Time After refueling, NIS indications

may be inaccurate

until calibration

at higher power levels.Therefore, NIS calibration

procedures

will reduce PRM trip setpoints from 109 to 60%to ensure that excore detectors do NOT contribute

to an overpower condition.(Rod Stop will remain at 103%).ReS loop!:l T indicators

should" be used for power indication

below 30%.[7]ENSURE Power Range high flux trip setpoints reduced to 60%in accordance

with following:

[C.3]*1,2-SI-ICC-092-N41.1

0*1,2-SI-ICC-092-N42.2

0*1,2-SI-ICC-092-N43.3

0*1,2-SI-ICC-092-N44.4

0 Instrument

Maintenance

Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 23 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

[8]ENSURE PRM calibration

values set to startup values.[C.3]Date----Reactor Engineer Time Date NOTE O-RT-NUC-OOO-003.0, Low Power Physics Testing is performed by RxEngineering

concurrently

with this procedure.

[9]RECORD estimated critical position calculated

in accordance

with 0-RT-NUC-OOO-003.0, Low Power Physics Testing.Estimated critical position: Boron concentration:

steps on bank ppm Initials Time Date[10]VERIFY Steps 5.2[1]through 5.2[9]completed.

[11]IF actual RCS boron concentration

does NOT approximately

equal estimated critical boron concentration

determined

in O-RT-NUC-OOO-003.0, THEN[11.1]DETERMINE the appropriate

boration/dilution

requirements

to achieve estimated boron conc.0[11.2]DILUTE/BORATE

in accordance

withO-SO-62-7

to the estimated critical boron concentration.

[C.12]0[11.3]OPERA TE pressurizer

heaters/spray

as necessary to equalize boron concentration (within 50 ppm)between reactor coolant loops and the pressurizer.

[C.12]0[11.4]WHEN sufficient

mixing has occurred, THEN OBTAIN a new boron sample.0[11.5]ENSURE actual boron concentration

is approximately

equal to the estimated critical boron concentration.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 24 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

Date----[12]RECORD minimum and maximum rod positions corresponding

to+/-1000 pcm ALLOWABLE LIMITS (Tech Spec Limit)determined

by 0-SI-NUC-000-001.0, Estimated Critical Conditions.

[C.11]Minimum allowable rod position Maximum allowable rod position steps on bank steps on bank Initials Time Date[13]VERIFY all shutdown rods are fully withdrawn in accordance

with O-SI-OPS-OOO-004.0, Surveillance

Requirements

Performed on Increased Frequency with no Specific Frequency, within 15 minutes prior to withdrawing

control rods.Time NOTE SR 4.1.1.4.a required verifying lowest T-avggreater

than or equal to 541°F within 15 minutes prior to achieving criticality.

[14]IF 0-SI-SXX-068-127.0

is NOT in progress, THEN INITIATE applicable

sections of 0-SI-SXX-068-127.0

to satisfy SR 4.1.1.4.a., Minimum Temperature

For Criticality.

Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 25 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

Date----[15]NOTIFY onsite personnel of reactor startup over PIA system.0 CAUTION Avoid operations

that could produce sudden changes of temperature

or unplanned boron-concentration

changes during approach to criticality

or low power.NOTES1)Nuclear instrumentation

shall be monitored very closely for indications

of unplanned reactivity

rate of change.[C.11]2)Activities

that can distract operators and supervisors

involved with reactor startup, such as shift turnover and surveillance

testing during approach to criticality, SHALL BE avoided.[C.12]3)ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for monitoring

NIS indications.

[16]MONITOR nuclear instruments

during approach to criticality:

[16.1]MONITOR source range and intermediate

range NIS to identify potential reactivity

anomalies.

[C.11][16.2]IF desired to place NR-45 recorder in fast speed, THEN ADJUST chart speed to high.D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 26 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)

CAUTION Do NOT exceed a steady startup rate of+1 DPM.NOTE The unit enters Mode 2 when the control banks are first withdrawn.

[17]INITIATE a reactor startup by performing

the following:

[17.1]RECORD both source range readings for ICRR base counts.N-31 CPS---.--.-N-32 CPS---Initials[17.2]RECORD intermediate

range readings.N-35 0/0---N-36 0/0---Initials[17.3]CALCULATE initial source range count doubling value USING Appendix C.MODE 2[17.4]INITIATE withdrawal

of control banks in accordance

with 0-80-85-1 to first stop point: CONTROL BANK A 128 STEPS[17.5]ENSURE Mode 2 entry is logged (log entry may be performed out of sequence later).o

SQN*UNIT STARTUP FROM HOT STANDBY O-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 27 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

[18]WHEN control bank A is at 128 steps, THEN PERFORM the following:

[18.1]STOP rod withdrawal.

[18.2]WAIT for approximately

two minutes.[18.3]NOTIFYRx Engineering

to perform ICRR calculation

in accordance

with

[C.11]CAUTION Date---Lowest loop T-avg must be verified greater than or equal to 541°F

15 minutes prior to achieving criticality.

NOTES1)Approximately

five to seven count doublings are expected to result in criticality.

However, criticality

should be anticipated

at any time.2)Proper bank overlap must be verified using 0-80-85-1 as each successive

rod bank is withdrawn.

[19]WHEN concurrence

obtained from Rx Engineering, THEN INITIATE rod withdrawal

to first count doubling (determined

in App.C)USING 0-80-85-1.

o

SQNUNITSTARTUP

FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 28 of 85 STARTUP No.Unit Date------5.2 Reactor Startup with Low Power Physics Testing (continued)

NOTE Steps 5.2[20]and 5.2[21]may be repeated as necessary if rod motion is stopped prior to reaching doubling value.[20]WHEN any of the following conditions

are met:*Source range count rate is approximately

equal to first doubling value determined

in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR*Operators orRx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[21]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor

concurrence

is o*btained to resume, THEN RESUME rod withdrawal

to first count doubling USING 0-80-85-1.

[22]IF source range count rate has reached or exceeded first doubling, THEN PERFORM the following:

[22.1]ENSURE rod motion STOPPED.[22.2]WAIT approximately

2-3*minutes to allow count rate to rise.DODD DODD[22.3]NOTIFY Rx Engineering

to perform leRR calculations

in accordance

with 0-RT-NUC-000-003.0.

[C.11]0[22.4]DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 29 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing-(continued)

[23]IF ICRR plot indicates criticality

will fall outside+/-1000 pcm ECC termination

band, THEN[23.1]NOTIFY SM and OutyPlant Manager.

EVALUATE if ECC should be recalculated

prior to continuing

startup.[23.3]IF startup must be aborted, THEN PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted.D[24]WHEN concurrence

obtained from Rx Engineering, THEN INITIATE rod withdrawal

to second doubling range (determined

in App.C)USING 0-SO-85-1.

NOTE Steps 5.2[25]and-5.2[26]may be repeated as n-ecessary

if rod motion is stopped prior to reaching doubling range.[25]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds second doubling range determined-in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.D DODD

DODD SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 30 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)

[26]IF rod motion was stopped prior to reaching doubling ra"nge AND Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

to second doubling range USING 0-SO-85-1.

[27]IF source range count rate has reached or exceeded second doubling range, THEN PERFORM the following:

[27.1]ENSURE rod motion STOPPED.[27.2]WAIT approximately

2-3 minutes to allow count rate to rise.[27.3]NOTIFY Rx Engineering

to perform ICRR calculations

in accordance

with 0-RT-NUC-000-003.0.

[C.11]0[27.4]DETERMINE new count doubling range USING Appendix C.[28]IF ICRR plot indicates criticality

will fall outside+/-1000 pcm ECC termination

band, THEN[28.1]NOTIFY SM and Duty Plant Manager.[28.2]EVALUATE if EGG should be recalculated

prior to continuing

startup.[28.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.D[29]IF leRR plot trend indicates acceptable

EGC, THEN INITIATE rod withdrawal

to third doubling range (determined

in App.G)USING 0-80-85-1.

D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 31 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

Date----NOTE Steps 5.2[30]and 5.2[31]may be repeated as necessary if rod motion is stopped prior to reaching doubling range.[30]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds third doubling range determined

in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[31]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor

concurrence

is obtaine*d to resume, THEN RESUME rod withdrawal

to third doubling range USINGO-SO-85-1.

[32]IF source range count rate has reached or exceeded third doubling range, THEN PERFORM the following:

[32.1]ENSURE rod motion STOPPED.[32.2]WA*IT approximately

2-3 minutes to allow count rate to rise.DODO DODD[32.3]NOTIFYRx Engineering

to perform leRR calculations

in accordance

with 0-RT-NUC-000-003.0.

[C.11]0[32.4]DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 32 of 85[33.1]NOTIFY SM and Duty Plant Manager.[33.2]EVALUATE if EGG should be recalculated

prior to continuing

startup.[33.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[34]IF ICRR plot trend indicates acceptable

ECG, THEN INITIATE rod withdrawal

USING 0-SO-85-1 to fourth doubling range (App.G)or criticality.

NOTE Steps 5.2[35]through 5.2[37]may be repeated as necessary if rod motion is stop*ped prior to reaching doubling range or criticality.

[35]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds fourth doubling range determined

in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR*Bank D rods reach fully withdrawn position OR D*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.DODD

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 33 of 85 STARTUP No.Unit Date----5.2.Reactor Startup with Low Power Physics Testing (continued)

[36]IF reactor is critical, THEN GO TO Step 5.2[59](N/A Steps 5.2[37]through 5.2[58]).[37]IF ALL of the following conditions

are met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank D rods are below fully withdrawn position*Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

USING 0-SO-85-1 to fourth doubling range or criticality (whichever

comes first).[38]IF source range count rate has reached or exceeded fourth doubling range, THEN PERFORM the following:

[38.1]ENSURE rod motion STOPPED.[38.2]WAIT approximately

2-3 minutes to allow count rate to rise.DODD[38.3]NOTIFY Rx Engineering

to perform ICRR calculations

in accordance

with 0-RT-NUC-000-003.0.

[C.11]0[38.4]DETERMINE new count doubling range US.ING Appendix C.[39]IF reactor is subcritical

with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical

with Rods Fully Withdrawn.

0

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 34 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)

[40]IF IGRR plot indicates criticality

will fall outside+/-1000 pcm EGG termination

band, THEN[40.1]NOTIFY SM*andDuty Plant Manager.[40.2]EVALUATE if EGG should be recalculated

prior to continuing

startup.[40.3]IF startup mustbe aborted, THEN PERFORM Appendix 0, Acti*ons if Reactor Startup Must Be Aborted.0[41]IF IGRR plot trend indicates acceptable

EGG, THEN INITIATE rod withdrawal

USING 0-SO-85-1 to fifth doubling range (App.G)or criticality.

NOTE Steps 5.2[42]throu.gh 5.2[44]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.

[42]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds fifth doubling range determined

in Appendix G OR*Bank D rods reach fully withdrawn position OR D*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[43]IF reactor is critical, THEN GO TO Step 5.2[59](N/A Steps 5.2[44]through 5.2[58]).DDDD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 35 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

[44]IF ALL of the following conditions

are met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank D rods are below fully withdrawn position*Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

USING 0-SO-85-1 to fifth*doubling range or criticality (whichever

comes first).[45]IF source range*count rate has reached or exceeded fifth doubling range, THEN PERFORM the following:

[45.1]ENSURE rod motion STOPPED.[45.2]WAIT approximately

2-3 minutes to allow count rate to rise.Date----DODO[45.3]NOTIFY Rx Engineering

to perform ICRR calculations

in accordance

with O-RT-NUC-000-003.0.

[C.11]0[45.4]DETERMINE new count doubling range USING Appendix C.[46]IF reactor is subcritical

with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical

with Rods Fully Withdrawn.

o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 36 of 85 STARTUP No.Unit Date--"-'_5.2 Reactor Startup with Low Power Physics Testing (continued)

[47]IF ICRR plot indicates criticality

will fall outside+/-1000 pcm ECG termination

band, THEN[47.1]NOTIFY SM and Duty Plant Manager.[47.2]EVALUATE if EGC should be recalculated

prior to continuing

startup.[47.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.D[48]IF ICRR plot trend indicates acceptable

ECC, THEN INITIATE rod withdrawal

USING 0-SO-85-1 to sixth doubling range (App.G)or criticality.

NOTE*Steps 5.2[49]through 5.2[51]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.

[49]WHEN any ofthefollowing

conditions

are met:*Source range count rate reaches or exceeds sixth doubling range determined

in Appendix C OR*Bank 0 rods reach fully withdrawn position OR D*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[50]IF reactor is critical, THEN GO TO Step 5.2[59](N/A Steps 5.2[51]through

5.2[58]).DDDD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 37 of 85 5'.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

[51]IF ALL of the following conditions

are met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank D rods are below fully withdrawn position*Unit Supervisor

concurrence

is obtaine*d to resume, THEN RESUME rod withdrawal

USING 0-SO-85-1 to sixth doubling range or criticality (whichever

comes first).[52]IF source range count rate has reached or exceeded sixth doubling range, THEN PERFORM the following:

[52.1]ENSURE rod motion STOPPED.[52.2]WAIT approximately

2-3 minutes to allow count rate to rise.Date----DODD[52.3]NOTIFY RxEngineeringto

perform ICRR calculations

in , accordance

with 0-RT-NUC-000-003.0.

[C.11]D[52.4]DETERMINE new count doubling range USING Appendix C.[53]IF reactor is subcritical

with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical

with Rods Fully Withdrawn.

D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 38 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

[54]IF IGRRplot indicates criticality

will fall outside+/-1000 pcm EGG termination

band, THEN[54.1]NOTIFY SM and Duty Plant Manager.[54.2]EVALUATE if ECG should be recalculated

prior to continuing

startup.Date------[54.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[55]IF IGRR plottrend indicates acceptable

EGG, THEN INITIATE rod withdrawal

to seventh doubling range (App.G)or criticality.

NOTE Steps 5.2[56]through 5.2[58]may be repeated as*necessary

if rod motion is stopped prior to reaching doubling range or criticality.

[56]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds seventh doubling range determined

in Appendix G OR*Bank D rods reach fully withdrawn position OR o*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[57]IF reactor is critical, THEN GO TOStep5.2[59](N/A Step 5.2[58]).DODD

SQN UNIT STARTUp*FROM HOT STANDBY O-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 39 of 85 5.2 STARTUP No.Unit---Reactor Startup with Low Power Physics Testing (continued)

[58]IF ALL of the following conditions

are met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank 0"rods are below fully withdrawn position Date----*Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

USING 0-SO-85-1 to seventh doubling range or criticality (whichever

comes first).0000[59]IF any of the following conditions

exist:*critical conditions

cannot be achieved within the+/-1 OOOpcm allowable limits OR*critical conditions

cannot be achieved above rod insertion limit OR*reactor startup must be aborted for other reasons, THEN PERFORM the following to abort rea.ctof startup:[C.11][59.1]STOP rod withdrawal.

[59.2]INITIATE insertion of control banks.[59.3.]PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted.[59.4]DO NOT CONTINUE this section.o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028*Page 40 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power PhysicsTesting(continued)

[60]IF reactor is subcritical

with Bank D rods at fully withdrawn position, THEN PERFORM Ap.pendix E, Actions if Reactor is Subcritical

with Rods Fully Withdrawn.

D[61]IF reactor is critical with SUR less than 0.3 DPM AND intermediate

range NIS is less than P-6 (1 X 10-4%), THEN PERFORM the following:

[61.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately

0.3 DPM.[61.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering

concurs withRCS dilution, THEN PERFORM RCS dilution (as recommended

by Rx Eng)to establish positive SUR of approx.0.3 DPM USING 0-SO-62-7.

SQN UNIT STARTUP FROM HOT STANDBY*0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 41 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)

I Start of Critical Step(s)NOTES 1)Blocking the SRM reactor trip with[HS-92-5001]

and[HS-92-50021

will disable the detector outputs and remove the audio count rate signal.2)Step 5.2[62]may be performed at time of criticalit¥, if required.Source range reactor trip must be BLOCKED before trip setpoints of 10 cps.[62]WHEN annunciator

XA-55-4A, window D-2 P-6 INTERMEDIATE

RANGE is LIT, THEN[C.2]PERMISSIVE

[62.1]RECORD both source range readings.N-31 CPS---N-32 CPS---Initials[62.2]RECORD both intermediate

range readings.N-35%RTP---N-36%RTP---Initials[62.3]VERIFY a minimum of one IRM channel greater than or equal to1X 10-4%RTP.[62.4]BL*OCK source range reactor trip by momentarily

placing[HS-92-5001]

and[HS-9.2-5002]

SRM TRIP RESET-BLOCK

P-6 handswitches

to BLOCK.D Initials Date Time

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 42 of 85 STARTUP No.Unit Date----5.2 Reactor Startup with Low Power Physics (continued)

[62.5]VERIFY annunciator

XA-55-4A, window C-1 SOURCE RANGE TRAINS A.&B TRIP BLOCK is LIT.D I End of Critical Step(s)[62.6]SELECT NR 45 to record one intermediate

range channel and one power range channel.[62.7]ADJ'UST NR 45 chart speed as desired.(N/A is no change needed.)[63]ENSUR*EPA announcement

made to notify plant personnel when the reactor is critical.NOTE D D When T-avg is less than 551°F and Tavg-Tref deviation alarm is lit, SR 4.1.1.4.b requires verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes.[64]IF Tavg-Tref deviation alarm[M-5A window C-6]is LIT AND T-avg is less than 551°F, THEN PERFORM 0-SI-SXX-068-127.0

to satisfy SR 4.1.1.4.b, Minimum Temperature

For Criticality.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 43 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)

[65]RAISE reactor power to approximately1X 10-3%:[65.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive S*UR of approximately

0.5 DPM(not to exceed 1 DPM).[65.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering

concurs with RCS dilution, THEN PERFORM RCS dilution (as recommended

by Rx Eng)to establish positive SUR ofapprox.0.5 DPM USING 0-SO-62-7.

[65.3]WHEN intermediate

rangeNls indicate approximately1X 10-3%, THEN PERFORM the following:

[65.3.1]STABILIZE reactor power using control rods.[65.3.2]RECORD critical data indicated below.Power Level: Rod Position: N-35%RTP--N-36__0/0 RTP RCS Boron concentration

Loop TAVG: Bank Step 1 Initials 2 Date 3 ppm 4 Time[66]MAINTAIN reactor power stable with control banks above*Iowinsertionlimit

USING rod movement or boration/dilution

to compensate

for Xenon.o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 44 of 85 STARTUP No.Unit Date---5.2 Reactor Startup with Low Power Physics Testing (continued)

[67]COORD.INATE

with Reactor Engineering

to perform Physics Testing USING O-RT-NUC-OOO-003.0.

0 NOTE If MSIVs are CLOSED, the reactor should be shut down to allow warming steam lines.[68]IF startup is to be discontinued

OR reactor startup was perf'ormed

with MSIVs closed, THEN GO TO 0-GO-6, Power Reduction From 30%Reactor Power to Hot Standby.[69]IF start up is to continue with one or both MFPTs available, THEN[69.1]ENSURE Steps 5.1[13]through 5.1[15]have been completed for applicable

pump(s).[69.2]VERIFY other applicable

actions Section 5.2 completed or initiated.

[69.3]GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5%Reactor Power.[70]IF start up is to continue with NO MFPT available, THEN[70.1]MARK Steps 5.1[13]through 5.1[17]as"N/A".END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICALRev.0028 Page 45 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing[1]VERIFY applicable

actions in Section 5.1 completed or initiated.

Date---NOTE Steps 5.3[3]through 5.3[8]may be performed out ofsequence.

[2]IF any MFPT trip buss is NOT energized, TH*EN[2.1]ENSURE requirements

of LCO 3.0.4 are satisfied.

[2.2]NOTIFY Unit 8RO that LCO 3.3.2.1 (3.3.2)action 20 will apply when Mode 2 is entered.[3]ENSURE Appendix*B, Mode 3 to Mode 2, 1 Review and Approval has been completed to ensure all restraints

to Mode 2, 1 entry have been resolved and approvals for mode change granted.[4]BLOCK Source Range High Flux At Shutdown alarm:[4.1]PLACE BOTH HI FLUX AT SHUTDOWN switches on M-13 to the BLOCK position.[4.2]VERIFY annunciator

XA-55-4B window C-1 , SOURCE RANGE HIGH SHUTDOWN FLUX ALARM is LIT.[C.2].

CLOCK 8M o[5]VERIFY greater than or equal to 0.5 cps on the highest reading SR instrument.

o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 46 of 85 5.3 STARTUP No.Unit_Reactor Startup without Physics Testing (continued)

NOTE Date---The following count rates may be used as a reference during the approach to criticality.

[6]RECORD SR count rates from two of the following:

[C.2](N/A instruments

not used)XI-92-5001A (N31)cps XI-92-5002A (N32)cps OR XI-92-5001

B XI-92-5002B (N31)(N32)___cps_______cps Time Date[7]IF conditions

exist which could cause Power RangeNIS indications

to be non-conservative, THEN ENSURE Power Range high flux trip setpoints reduced to 60%in accordance

with the following:

[C.3]*1,2-SI-ICC-092-N41.1

0*1,2-SI-ICC-092-N42.2

0*1,2-SI-ICC-092-N43.3

0*1,2-SI-ICC-092-N44.4

0 Instrument

Maintenance

Date Time

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 47 of 85.5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[8]VERIFY the estimated critical position calculated

in accordance

with O-SI-NUC-000-001.0, Estimated Critical Conditions.

Date----Estimated critical position: Assumed boron concentration:

steps on bank ppm Initials STA Time Time Date Date[9]VERIFY*Steps 5.3[1]through 5.3[8]completed.

[10]IF estimated critical boron concentration

does NOT approximately

equal actual boron concentration, THEN[10.1]DETERMINE the appropriate

boration/dilution

requirements

to achieve criticality

within acceptable

limits.D[10.2]DILUTE/BORATE

in accordance

with 0-80-62-7 to the estimated critical boron concentration.

[C.12]0[10.3]OPERATE pressurizer

heaters/spray

as necessary to equalize boron concentration (within 50 ppm)between reactor coolant loops and the pressurizer.

[C.12]D[to.4]WHEN sufficient

mixing has occurred, THEN OBTAIN a new boron sample.D[10.5]ENSURE actual boron concentration

is approximately

equal to the estimated critical boron concentration.

SQN UN*IT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 48 of 85 STARTUP No.----Unit---Date----5.3 Reactor Startup without Physics Testing (continued)

NOTE Termination

limits are associated

with+/-750 pcm tolerance band.These values are within minimum and maximum rod positions corresponding

to Tech Spec limit of+/-1000 pcm (Minimum and Maximum Allowable Limits).Termination

limits shall be used by Reactor Engineering

and Operations

to determine whether approach to criticality

should be terminated

and a new ECC calculated.

ECC must be terminated

if Minimum or Maximum Allowable Limits (corresponding

to Tech Spec limit of+/-1000 pcm)are approached.

[11]RECORD upper and lower rod position limits corresponding

to+/-750 pcm Termination

Band as determined

by 0-SI-NUC-000-001..0, Estimated Critical Conditions.

Upper termination

rod position Lower termination

rod position steps on bank steps on bank Initials Time Date[12]RECORD minimum and maximum rod positions corresponding

to+/-1000 pcm ALLOWABLE LIMITS (Tech Spec Limit)determined

by 0-SI-NUC-000-001.0, Estimated Critical Conditions.

[C.11]Minimum allowable rod position Maximum allowable rod position steps on*bank steps on bank Initials Time Date[13]VERIFY all shutdown rods are fully withdrawn in accordance

with 0-SI-OPS-000-004.0, Surveillance

Requirements

Performed on In'creased

Frequency with no Specific Frequency, within 15 minutes prior to withdrawing

control rods.Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 49 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

NOTE Date----SR 4.1.1.4.a requires verifying lowest T-avggreater

than_or equal to 541°F within 15 minutes prior to achieving criticality.

[14]IF O-SI-SXX-068-127.0

is NOT in progress, THEN INITIATE applicable

sections of O-SI-SXX-068-127.0

to satisfy SR 4.1.1.4.a., Minimum Temperature

For Criticality.

[15]NOTIFY onsite personnel of reactor startup over PIA system.D CAUTION Avoid operations

that-could

produce sudden changes of temperature

or unplanned boron concentration

changes during approach to criticality

or low power.NOTES 1)Nuclear instrumentation

shall be monitored very closely for indications

of unplanned reactivity

rate of change.[C.11]2)Activities

that can distract operators and supervisors

involved with reactor startup, such as shift turnover and surveillance

testing during approach to criticality, SHALL BE avoided.[C.12]3)ICS points N0031A, N0032A, N0035A, and N0036A may be used as an aid for monitoring

NIS indications.

[16]MONITOR nuclear instruments

during approach to criticality:

[16.1]MONITOR source rang-e and intermediaterangeNIS to identify potential reactivity

anomalies.

[C.11][16.2]IF desired to placeNR-45

recorder in fast speed, THEN ADJUST chart speed to high.D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 50 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

CAUTION Date---Do NOT exceed a steady startup rate of+1 DPM.NOTE The unit enters Mode 2 when the control banks are first withdrawn.

[17]INITIATE a reactor startup by performing

the following:

[17.1]RECORD*both source range readings for ICRR base counts.N-31 CPS---N-32 CPS---Initials[17.2]RECORD intermediate

range readings.N-35 0/0---N-36 0/0---Initials[17.3]CALCULATE initial source range count doubling value USING Appendix C.MODE 2[17.4]INITIATE withdrawal

of control banks in accordance

with 0-SO-85-1 to first stop point: CONTROL BANK A 128 STEPS[17.5]ENSURE Mode 2 entry'is logged (log entry may be performed out of sequence later).o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 51 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[18]WHEN control bank A is at128 steps, THEN PERFORM the following:

[18.1]STOP rod withdrawal.

[18.2]WAIT for approximately

two minutes.[18.3]N'OTIFY Rx Engineering

to perform ICRR calculation

in accordance

with 0-81-NUC-OOO-001.0.

[C.11]CAUTION Date---Lowest loop T-avg must be verified greater than or equal to 541°F using 0-SI-SXX-068-127.0within

15 minutes prior to achieving criticality.

NOTES1)Approximately

five to seven count doublings are expected to result in criticality.

However, criticality

should be anticipated

at.a*ny time.2)Proper bank overlap must be verified using 0-80-85-1 as each successive

rod bank is withdrawn.

[19]WHEN concurrence

obtained from Rx Engineering, THEN INITIATE rod withdrawal

to first count doubling (determined

in App.C)USING 0-80-85-1.

D

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 52 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

Date---NOTE Steps 5.3[20]and 5.3[21]may be repeated as necessary if rod motion is stopped prior to reaching doubling value.[20]WHEN any of the following conditions

are met:*Source range count rate is approximately

equal to first-doubling

value determined

in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-80-85-1)

OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[21]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

to first count doubling USING

[22]IF source range count rate has reached or exceeded first doubling, THEN PERFORM the following:

[22.1]ENSURE rod motion STOPPED.[22.2]WAIT approximately

2-3 minutes to allow count rate to rise.DODD DODD[22.3]NOTI*FYRx Engineering

to perform ICRR calculations

in accordance

with O-SI-NUC-000-001.0.

[C.11]D[22.4]DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 53 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continu.ed)

[23]IF ICRR plot indicates criticality

will fall outside+/-750 pcm ECC termination

band, THEN[23.1]NOTIFY SM and Duty Plant Manager.[23.2]EVALUATE if ECC should be recalculated

prior to continuing

startup.Date----[23.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.D[24]WHEN concurrence

obtained from Rx Engineering, THEN INITIATE rod withdrawal

to second doubling range (determined

in App.C)USING 0-80-85-1.

NOTE Steps 5.3[25]and 5.3[26]may be repeated as necessary if rod motion is stopped prior to reaching doubling range.[25]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds second doubling range determined

in Appendix C OR*C'ontrol bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.o DODD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 54 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[26]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

to second doubling range USING 0-SO-85-1.

[27]IF source range count rate has reached or exceeded second doubling range, THE*N PERFORM the following:

[27.1]ENSURE rod motion STOPPED.[27.2]WAIT approximately

2-3 mi'nutes to allow count rate to rise.Date---0000[27.3]NOTIFY Rx Engineering

to perform ICRR calculations

in accordance

with 0-SI-NUC-000-001.0.

[C.11]0[27.4]DETERMINE new count doubling range USING Appendix C.[28]IF ICRR plot indicates criticality

will fall outside+/-750 pcm ECC termination

band, THEN[28.1]NOTIFYSM and Duty Plant Manager.[28.2]EVALUATE if ECC should be recalculated

prior to continuing

startup.[28.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[29]IF ICRR plot trend indicates acceptable

ECC, THEN IN'ITIATE rod withdrawal

to third doubling range (determined

in App.C)USINGO-SO-85-1.

o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 55 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

Date----NOTE Steps 5.3[30]and 5.3[31]may be repeated as necessary if rod motion is stopped prior to reaching doubling range.[30]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds third doubling range determined

in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-SO-85-1)

OR*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[31]IF rod motion was stopped prior to reaching doubling range AND Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

to third doubling range USING 0-SO-85-1.

[32]IF source range count rate has reached or exceeded third doubling range, THEN PERFORM the following:

[32.1]ENSURE rod motion STOPPED.[32.2]WAIT approximately

2-3 minutes to allow count rate to rise.DODD DODD[32.3]NOTIFY Rx Engineering

to perform leRR calculations

in accordance

with

[C.11]0[32.4]DETERMINE new count doubling range USING Appendix C.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 56 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[33]IF ICRR plot indicates criticality

will fall outside+/-750 pcm ECC termination

band, THEN

NOTIFY SM and Duty Plant Manager.[33.2]EVALUATE if ECC should be recalculated

prior to continuing

startup.Date---[33.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.0[34]IF ICRRplot trend indicates acceptable

ECC, THEN INITIATE rod withdrawal-USING

0-80-85-1 to fourth doubling range (App.C)or criticality.

NOTE Steps 5.3[35]through 5.3[37]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.

[35]WHEN any of the foHowing conditions

are met:*Source range count rate reaches or exceeds fourth doubling range determined

in Appendix C OR*Control bank being withdrawn reaches 128 steps (requires verifying overlap in 0-80-85-1)

OR*Bank D rods reach fully withdrawn position OR o*Operators or Rx Engineer determine that rod motion shoul-d be stopped THEN STOP outward rod motion.DOOD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 57 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[36]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Steps 5.3[37]through 5.3[58]).[37]I*F ALL of the following conditions

are met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank D rods are below fully withdrawn position*Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

USING 0-SO-85-1 to fourth doubling range or criticality (whichever

comes first).[38]IF source range count rate has reached or exceeded fourth doubling range, THEN PERFORM the following:

[38.1]ENSURE rod motion STOPPED.[38.2].WAIT approximately

2-3 minutes to allow count rate to rise.*Date----DODD[38.3]NOTIFY Rx Engineering

to perform leRR calculations

in accordance

with O-SI-NUC-OOO-001.0.

[C.11]D[38.4]DETERMINE new count doubling range USING Appendix C.[39]IF reactor is subcritical

with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical

with Rods Fully Withdrawn.

D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 58 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[40]IF ICRR plot indicates criticality

will fall outside+/-750 pcm ECC terminati*on

band, THEN[40.1]NOTIFY SMand Duty Plant Manager.[40.2]EVALUATE ifECC should be recalculated

prior to continuing

startup.Date---[40.3]IF startup must be aborted, THEN PERFO*RM Appendix 0, Actions if Reactor Startup Must Be Aborted.D[41]IF ICRR plot trend indicates acceptable

ECC, THEN INITIATE rod withdrawal

U5INGO-SO-85-1

to fifth doubling range (App.C)or criticality.

NOTE Steps 5.3[42]through 5.3[44]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.

[42]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds fifth doubling range determined

in Appendix C OR*Bank D rods reach fully withdrawn position OR D*Operators orRx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[43]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Steps 5.3[44]through 5.3[58]).DDDD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 59 of 85 5.3 STARTUP No.Unit------Reactor Startup without Physics Testing (continued)

[44]IF ALL of the following conditions

are met:*rod motion was stopped'prior to reaching doubling range or criticality

  • Bank.D rods are below fully withdrawn position*Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

USING 0-SO-85-1 to fifth doubling range or criticality (whichever

comes first).[45]IF source range count rate has reached or exceeded fifth doubling range, THEN PERFORM the following:

[45.1]ENSURE rod motion STOPPED.[45.2]WAIT approximately

2-3 minutes to allow count rate to rise.Date---DOOO[45.3]NOTIFY Rx Engineering

to perform ICRR calculations

in accordance

with O-SI-NUC-OOO-001.0.

[C.11]D[45.4]DETERMINE new Gount doubling range USING Appendix C.[46]IF reactor is subcritical

with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if Reactor is Subcritical

with Rods Fully Withdra*wn.

0

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 60 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[47]IF IGRR plot indicates criticality

will fall outside+/-750 pcm EGG termination

band, THEN[47.1]NOTIFY SM and Duty Plant Manager.[47.2]EVALUATE if EGO should be recalculated

prior to continuing

startup.Date---[47.3]IF startup must be aborted, THEN PERFORM Appendix 0, Actions if Reactor Startup Must Be Aborted.0[48]IF IGRR plot trend indicates acceptable

EGG, THEN INITIATE rod withdrawal

USING 0-SO-85-1 to sixth doubling range (App.G)or criticality.

NOTE Steps 5.3[49]through 5.3[51]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.

[49]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds sixth doubling range determined

in Appendix C OR*Bank 0 rods reach fully withdrawn position OR o*Operators or Rx Engineer determine that rod motion should be stopped THEN STOP outward rod motion.[50]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Steps 5.3[51]through 5.3[58]).DODD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 61 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[51]IF ALL of the following conditions

are met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank D rods are below fully withdrawn position*Unit Supervisor

concurrence

is obtained to resume, THEN RESUME rod withdrawal

USING 0-80-85-1 to sixth doubling range or criticality (whichever

comes first).[52]IF source ran'ge count rate has reached or exceeded sixth doubling range, THEN PERFORM the following:

[52.1]ENSURE rod motion STOPPED.[52.2]WAIT approximately

2-3 minutes to allow count rate to rise.Date----DDDD[52.3]NOTIFY Rx Engineering

to perform ICRR calculations

in accordance

with 0-SI-NUC-000-001.0.

[C.11]0[52.4]DETERMINE new count doubling range USING Appendix C.[53]IF reactor is subcriUcal

with Bank D rods at fully withdrawn position, THEN PERFORM Appendix E, Actions if"Reactor is Subcritical

with Rods Fully Withdrawn.

D

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 62 of 85 5.3 STARTUP No.UnitReactor Startup without Physics Testing (continued)

[54]IF ICRR plot indicates criticality

will fall outside+/-750 pcm ECC termination

band, THEN[54.1]NOTIFY SM and Duty Plant Manager.[54.2]EVALUATE if ECC should be recalculated

prior to continuing

startup.Date---[54.3]IF startup must be aborted, THEN PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.O'[55]IF ICRR plot trend*indicates

acceptable

ECC, THEN INITIATE rod withdrawal

USINGO-SO-85-1

to seventh doubling range (App.C)or criticality.

NOTE Steps 5.3[56]through 5.3[58]may be repeated as necessary if rod motion is stopped prior to reaching doubling range or criticality.

[56]WHEN any of the following conditions

are met:*Source range count rate reaches or exceeds seventh doubling range determined

in Appendix C OR*Bank D rods reach fully withdrawn position OR D*Operators or RxEng.ineer

determine that rod motion should be stopped THEN STOP outward rod motion.[57]IF reactor is critical, THEN GO TO Step 5.3[59](N/A Step 5.3[58]).DODD

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR'CRITICAL Rev.0028 Page 63 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

[58]IF ALL of the followingconditionsare

met:*rod motion was stopped prior to reaching doubling range or criticality

  • Bank D rods are below fully withdrawn position Date----*Unit Supervisor

concurrence

is obtained to resume, THEN RES*UME rod withdrawal

USING 0-SO-85-1 to seventh doubling range or criticality (whichever

comes first).0000[59]IF any of the following conditions

exist:*critical co.nditions

cannot be achieved within the+/-750 pcm termination

band OR*critical conditions

cannot be achieved within the+/-1 000 pcm allowable limits OR*critical conditions

cannot be achieved above rod insertion limit OR*reactor startup must be aborted for other reasons, THEN PERFORM the following to abort reactor startup:[C.11][59.1]STOP rod withdrawal.

[59.2]INITIATE insertion of control banks.[59.3]PERFORM Appendix D, Actions if Reactor Startup Must Be Aborted.[59.4]DO NOT CONTINUE this section.o

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 64 of 85 STARTUP No.

Unit---Date---5.3 Reactor Startup without Physics Testing (continued)

[60]IF reactor is subcritical

with BankO rods at fully

THEN PERFORM Appendix E, Actions if Reactor is Subcritical

with Rods Fully Withdrawn.

0[61]IF reactor is critical with SUR less than 0.3 DPM AND intermediate

range NIS is less than (1 X 10-4%), THEN PERFORM the following:

[61.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately

0.3 DPM.[61.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering

concurs with RCSdilution, THEN PERFORM RCS dilution (as recommended

by Rx Eng)to establish positive SUR of approx.0.3 OPM USING 0-80-62-7.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 65 of 85 5.3 STARTUP No.Unit---Reactor*Startup

without Physics Testing (continued)

I Start of Critical Step(s)Date---NOTES 3)Blocking the SRM reactor trip with[HS-92-50011

and[HS-92-50021

will disable the detector outputs and remove the audio count rate signal.4)Step 5.3[62]may be performed at time of criticality, if required.Source range reactor trip must be BLOCKED before trip setpoint of 10 5 cps.[62]WHEN annunciator

XA-55-4A, window 0-2 P-6 INTERMEDIATE

RANGE PERMISSIVE

is LIT, THEN[C.2][62.1]RECORD both source range readings.N-31 CPS---N-32 CPS---Initials[62.2]RECORD both intermediate

range readings.N-35%RTP N-36%RTP Initials[62.3]VERIFY a minimum of one IRMchannel

greater than or equal to1X 10-4%RTP.0[62.4]BLOCK source range reactor trip by momentarily

placing[HS-92-50011

and

SRM TRIP RESE*T-BLOCK P-6 handswitches

to BLOCK.Initials Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO-REACTOR CRITICAL Rev.0028 Page 66 of 85 Date---5.3 SOURCE RANGE TRAINS A&B TRIP BLOCK is LIT.o I End of Critical Step(s)[62.6]SELECT NR 45 to record one intermediate

range channel and one power ran-ge channel.[62.7]ADJUST NR45 chart speed as desired.(N/A if no change needed).[63]ENSURE PA announcement

made to notify plant personnel when the reactor is critical.NOTE D D o When T-avg is less than 551°F and Tavg-Tref deviation alarm is lit, SR 4.1.1.4.b requires verifying lowest T-avg greater than or equal to 541°F at least once per 30 minutes.[64]IF Tavg-Tref deviation alarm[M-5A window C-6]is LIT AND T-avg is less than 551°F, THEN PERFORM O-SI-SXX-068-127.0

to satisfy SR 4.1.1.4.b, Minimum Temperature

For Criticality.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 67 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

,[65]RAISE reactor power to approximately

1X 10-3%:[65.1]IF Bank D control rods are BELOW fully withdrawn position, THEN OPERATE control rods to establish a positive SUR of approximately

0.5 DPM (not to exceed 1 DPM).[65.2]IF Bank D rods have reached fully withdrawn position AND Rx Engineering

concurs with RCS dilution, THEN PERFORM RCS dilution (as recommended

by Rx Eng)to establish positive SUR of approx.0.5 DPM USING 0-SO-62-7.

[65.3]WHEN intermediate

range NIS indicate approximately1X 10-3%, THEN PERFORM the following:

[65.3.1]STABILIZE reactor power using control rods.[65.3.2]RECORD critical data indicated below.Date----Power Level: N-35%RTP---N-36%RTP---Rod Position: RCS Boron concentration

Loop TAVG: Bank 1 Step 2 3 Initials ppm 4 Time Date[66]VERIFY control rods above rod ins*ertion

limit USING 1,2-SI-OPS-OOO-002.0, Shift Log.[67]MAINTAIN reactor power stable with control banks above low insertion limit USING rod movement or boration/dilution

to compensate

for Xenon.o o

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 68 of 85 5.3 STARTUP No.Unit---Reactor Startup without Physics Testing (continued)

Date---NOTE If MSIVs are CLOSED, the reactor should be shut down to allow warming steam lines.[68]IF startup is to be discontinued

OR reactor startup was performed with MSIVs closed, THEN GO TO 0-GO-6, Power Reduction From 30%Reactor Power to Hot Standby.[69]IF start up is to continue with one or bothMFPTs available, THEN[69.1]ENSURE Steps 5.1[13]through 5.1[15]have been completed for applicable

pump(s).[69.2]VERIFY other applicable

actions in Section 5.3 completed or initiated.

[69.3]GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5%Reactor Power.[70]IF start up is to continue with NO MFPT available, THEN[70.1]MARK Steps 5.1[13]through 5.1[17]as"N/A".[70.2]VERIFY other applicable

actions in Section 5.3 completed or initiated.

[70.3]GO TO 0-GO-3, Power Ascension From Reactor Critical to Less Than 5%Reactor Power.END OF TEXT

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 69 of 85 6.0 RECORDS Completed copies shall be transmitted

to the Operations

Superintendent's

Secretary.

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 70 of8S Appendix A (Page 1 of 1)DELETED 1.0 DELETED

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 71 of 85 1.0 Appendix B (Page 1 of 8)MODE 3 TO MODE 2,1 REVIEW AND APPROVAL STARTUP No.Unit------'--MODE 3 TO 2,1 REVIEW AND APPROVAL

NOTE Steps in this Appendix may be performed out of sequence, except for those steps that pertain to the Operations

Superintendent

Hold Point.[1]PRIOR to entering Mode 2, 1, an SRO shall review the following:

NOTE Mode 3 to Mode 2, 1 Checklist and Reactor Trip Breaker Checklist are to be attached to this instruction.

tJ{;Vo Time A.Mode 3 to Mode 2,1 Checklists

from the responsible

sections and DETERMINE thatthe required surveillance

testing for Mode 2 entry has been co pleted

Da e Of&00YO Time.jO].C2?'1 0 Time c.Active clearances

for mode ch nge restraints.

I 1 B.Reactor Trip Breaker Closure C'ecklists from the responsible

sections and DETE*RMINE

that required surveillance

testing for mode change has been completed.

l D.TACF Books for outstanding

alternations

on systems prior to declaring a T.S.system or comp: ent 0 e ble.[C.10]!01 Time at

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 72 of 85

1.0 Appendix B (Page 2 of 8)STARTUP No.Unit J----1('----

MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)

E.O-TI-EXX-OOO-001.0, Electrical

Jumper Control Log to determine if any potential T.S.restriction

exists which would prevent a mode chang*f1jJ i2ill Time tJ/Iv 1/j,.;F.Active Procedures

Book to determine equipment status that may be abnormal.nri G Unql()Time (j1VJ Time G.OPDP-4, Annunciator

Disablement

Log for alarms affecting operability

of equipment required for mode change.H.O-PI-OPS-301-001.0Plant

Computer Point Disablement

Log for alarms affecting operability

of equipment required for mode change.I.Board walkdown is completed to verify proper equipment alignment.(Refer to appropriate

CRO and GATC Pis for guidance)[C.10]OJ..61/v;<,./uf*(//ylJ

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 73 of 85 1.0 Appendix B (Page 3 of 8)STARTUP No.Unit+MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)

NOTE Tech Spec and TRM LCO 3.0.4 govern entering Mode 2 if,any LCO requirement

applicable

in Mode*2is not met.Therefore, mode change is not allowed while in a Tech Spec or TRMaction UNLESS the exceptions

and/or allowances

stated in LCO 3.0.4 can be applied.J.RE*VIEW all Tech Spec and TRM Actions which have been entered on the affected unit and common equipment to verify that mode change is acceptable.

SRO SRO Time Time Date Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 74 of 85 2.0 Appen.dix B (Page 4 of 8)STARTUP No.UnitDEPARTMENT

MANAGERS REVIEW 2.1 Periodic Test Coordinator:

.Instrument

Maintenance:

°tXr/o f ate OZIO Time PiOdlC Test Coordinator

ENSURE that all surveillance

requirements

for m de 2 entry are updated and included Withiit e c!han checklist.

.i./&/0 7t i dic Te oordinator

Time ENSURE that all surveilianceV:eqUirements

for Reactor Trip Breaker Closure Checklist are updated and included within the checklist.

[e.9][2][1]2.2[1]ENSURE Wide Range SG Level Recorders[LR-3-43A]

and[LR-3-98A]areOPERABLE

and SET to a range requested by the operator.(Recommended

range between 80 and 90%of scale).[C.6]

4JfIOJ Time'at 2.3 Fire Ops Section:[1]Oil%

Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 75 of 85 Appendix B (Page 5 of 8)I Unit----'--STARTUP No.____2.4 Systems Engineering

Section:[1]REVIEW of mode change checklist is complete and all surveillance

requirements

have met their acceptance

criteria for Mode 2 entry.Shift Manager[2]REVIEW of Reactor Trip Breaker Closure Checklist is complete, all surveillance

requirements

have met their acceptance

criteria, and all open items that affect modechangehave

been closed.Time Date Shift Manager Time Date NOTE The evaluation

made by the Systems Engineer in the next step will prevent thermal shock to the PZR spray nozzle.[3]ENSURE PZR spray line bypass valves are throttled to maintain acceptable

spray line temperature*

in accordance

with 0-SO-68-3.

f£JYWL&1f;t;System En'gineering

Time orfr;fal ate[4]IF startup is following a refueling outage, THEN ENSURE Present Cycle Core Operating Limit Report are inserted in the unit's Technical specU/oon

C.7]r If!f f f...ilsing

or designee OGO(

1 0)Time ate f'

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 76 of 85 2.5 STARTUP No.----Maintenance

Section: Appendix B (Page 6of8)Unit-l-Date fJ tjV;;/Ol[1]REVIEW of mode change checklist is complete and all surveillance

requirements

have met their acceptance

criteria for Mode 2 entry.Shift Manager[2]REVIEW of Reactor Trip Breaker Closure Checklist is complete, aH surveillance

requirements

have met their acceptance

criteria, and all open items that affect mod"e change have been closed.Shift Manager 2.6 Chemistry Section: NOTE Time Time Date Date The following step does not require a new analysis to be performed for this startup.Routine analysis is sufficient

unless there is reason to suspect chemistry has been changed.[1]ENSURE reactor coolant chemistry within limits of Technical Requirements

Manual 3.4.7 as determined

by the Chemical Shift Supervisor.

4 obJO*J

oj Time

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 77 of 85 Appendix B (Page 7 of 8)3.0 STARTUP No.Unit---SHIFT MANAGER (SM)HOLD POINT[1]ENSURE Tech Spec and non-Tech Spec work related activities

are completed or will not prohibit entry or impact continued operation in Mode 2.Date8M Time Date[2]ENSURE no open DCN/ECNsthat

would prohibit a mode change.(SM concurrence

with the Modifications

Manager or designee).

SM Time Date[3]REVIEW all open work activities

relative to the unit for the purpose of identifying

maintenance

activities

that could affect system operability

prior to mode change SM[4]IF any potential Tech Spec.mode constraint

exists, THEN OBTAIN Operations

Superintendent

resolution

prior to proceeding

with the mode change SM Time Time Date Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 78 of 85 Appendix B (Page 8 of 8)3.0 STARTUP No.Unit---SHIFT MANAGER (8M)HOLD POINT (continued)

[5]IF the startup follows a reactor trip or an emergency shutdown, THEN Date---A.ENSURE cause of the trip/shutdown

has been determined

and will not impact Mode 2 entry.SM B.ENSURE Reactor trip report is complete.Time Date (0-TI-QXX-000-001.0, Event Critique, Post Trip Report, Equipment Root Cause and Outage Milestone PER Evaluation)

SM Time Date c.ENSURE 0-GO-12, Realignment

of Secondary Equipment Following Reactor TriplTurbine

Trip/Emergency

shutdown, is complete.SM Time Date 4.0 OPERATIONS

SUPERINTENDENT

HOLD POINT Operations

Superintendent

or his designee concurs and grants approval to proceed to Mode 2, 1.Operations

Superintendent

Time Date

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 79 of 85 Appendix C (Page 1 of 1)DETERMINING

SOURCE RANGE COUNT RATE DOUBLING 1.0 CALCULATING

DOUBLING RANGE NOTES1)Source range reading shal.l be allowed to stabilize for approximately

3 minutes after each reactivity

change prior to determining

new stable count rate.2)The highest reading channel should be used when determining

stable count rate.3)Doubling range is used to determine when rod motion should be stopped during approach to criticality.

Criticality

is expected in about 5 to 7 count rate doublings.

4)This appendix may be performed and IV'd by operators, ST A, or Rx Engineers.

STABLE COUNT RATE DOUBLING RANGE INITIALS COUNT RATE (CR)CR X 1.75=CR X 2.0=1st IV (Lower value not used for first doubling)End of Section

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 80 of 85 Appendix D (Page 1 of 1)ACTIONS IF REACTOR STARTUP MUST BE ABORTED 1.0 STARTUP No.OPERATOR ACTIONS Unit---CAUTION Date---If reactor trip is required, E-O should be performed instead of this appendix.[1]ENSURE all control bank rods FULLY INSERTED in accordance

with 0-SO-85-1.

[2]LOG Mode 3 entry in narrative log.[3]VERIFY adequate shutdown margin in accordance

with 0-SI-NUC-000-038.0.

[4][5]Initials DETERMINE and CORRECT cause of the discrepancy.

WHEN reactor startup is to resume, THEN PERFORM the following:

[5.1]RECALCULATE-estimated

critical conditions

in accordance

with 0-RT-NUC-000-003.0(Startup

after refueling)

or 0-SI-NUC-000-001.0 (Startup after non-refueling

outage).Time Date o[5.2]DILUTE/BORATE

in accordance

withO-SO-62-7

to the estimated critical boron concentration.

[C.12][5.3]EQUALIZE boron concentration (within 50 ppm)between reactor coolant loops and pressurizer

by operating pzr heaters and spray.[C.12][5.4]R-E-INITIATE

0-GO-2.End of Document

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 81 of 85 Appendix E (Page 1 of 2)ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY

1.0 OPERATOR ACTIONS NOTE Allowable upper limit for critical position may be above the fully withdrawn position on Bank D.If Reactor Engineering

determinesthatcore response is within acceptable

limits, this appendix allows RCS dilution to assist in achieving criticality.

[1]CONSULT Reactor Engineering

to determine if core response is within acceptable

limits.D[2]IF projected critical rod position exceeds+1000 pcm limit OR startup will be aborted due to failing to achieve criticality, THEN[2.1][2.2]PERFORM AppendixD, Actions if Reactor Startup Must Be Aborted..DO NOT CONTINUE this appendix.D D[3]ENSURE control bank D inserted to less than or equal to estimated critical position determined

in O-RT-NUC-000-003.0 (Startup after refueling)

or O-SI-NUC-000-001.0 (Startup after non-refueling

outage).[4]DETERMINE dilution volume to increase core reactivity

by 100 pcm OR as recommended

by Rx Engineering.

gallons-----Rx Engineer IV

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 UnitO TO REACTOR CRITICAL Rev.0028 Page 82 of 85 Appendix E (Page 2 of 2)1.0 STARTUP No.Unit------OPERATOR ACTIONS (continued)

CAUTION Date---NISindications

should be carefully monitored during and following dilution.[5][6]PERFORM specified dHution USING 0-80-62-7.

WHEN at least30 minutes has elapsed for ReS mixing AND RxEngineer

concurs with resuming startup, THEN RETURN to appropriate

step (based on number of doublings)

in Sect.5.2 (Startup after refueling)

or Section 5.3 (Startup after non-refueling

outage).End of Document D D

SQN UNIT STARTUP FROM HOT STANDBY O-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 83 of 85 Source Notes (Page 1 of 3)Requirements

Statement Verify MFWP trip bus energized before entry into Mode 2.Revise GOI-2 to require verification

of intermediate

range (IR)status at approximately

20 and 25 percent, verify source range (SR)status and channel check at lower power, monitor core delta Ts at low-power levels and during power escalation

and compare with N IS response, and verify that the IR rod stop and trip bistables come in at the appropriate

power level during power ascension.

Following refueling operations

relocation

of NIS or modifications

affecting the NIS response, provide adequate reductions

of trip setpoint and limitations

of reactor power until accuracy of the NIS is verified.Also, provide alternate indications

of power independent

of calorimetric

calculations

during power ascensions.

Decommitted

3/12/99 Assurance that TSC computer is reset prior to startup;defines"reset" and"updating".(Modified C.5 permitting

relaxing requirement.)

Provisions

to ensure that enhanced steam generator level recorders are operable in the main control room prior to entering mode 2.Source Document LER 328/88-014

NCO 890118002 LER 328/89006 S53 890531 844 JRBto NRC SOER-90-003

NCO 900107009 NER 1187001 LER 327/90011R1

Verbal commitment

to NRC at SNP Meeting 10/04/90 NCO 890097004 L44 890505 805 Implementing

Statement C.1 C.2 C.3 C.4 C.S C.6

SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2 Unit 0 TO REACTOR CRITICAL Rev.0028 Page 84 of 85 Source Notes (Page 2 of 3)Requirements

Statement Based upon the requirements

of the May 6, 1991 PORC meeting this verification

has been added to implement the referenced

Technical Specification

change for the Core Operating Limits Report.Consult Reactor Engineerin*g

for guidance during evolutions

of unusual power maneuvers at end of core life.Provide reactor trip breaker closure checklists

to ensure all surveillance

requirements

for reactor trip breaker closure are satisfied.

Revise

to include a step signoff with the T ACF review, hold order review etc.section of GOI, for the Duty SOS to ensure a board walkdown to verify proper alignment is performed by a designated

  • SRO prior to mode change.Op*erations

startup procedures

should:1)Stress conservative

actions and compliance

with written procedures

when repositioning

control rods, 2)Guidance on actions whe.n criticality

will be achieved outside the ECC tolerance band, 3)Avoid activities

which distract the operators, 4)Directions

to use pertinent instrumentation

to monitor approach to criticality, 5)Periodic pauses during rod withdrawal.

Source Document PORC Minutes#50880 5/06/91T/891-08

NER 89 0794 OER 89 3497U1 C5 Outage Critique item 118-92-045

80ER 88-02 NER 88047400 Implementing

Statement C.7 C.8 C.g C.10 C.11

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 2 of 77 TABLE OF CONTENTS Page 1 of 2 Section Title Page 1.0 INTRODUCTION

"......................................................................

4 1.1 Purpose......

4 1.2 Scope................................................................................................................

4 2.0 REFERENCES..................................................................................................

4 2.1 Performance

References..................................................................................

4 2.2 Developmental

References...............................................................................

4 3.0 PRECAUTIONS

AND LIMITATIONS................................................................

6 4.0 PREREQUISITE

ACTIONS..9 5.0 STARTUP/STANDBY

READINESS 10 5.1 Placing MG Set(s)in Standby Readiness............................

10 5.1.1 Placing MG Set A In Service With MG Set B NOT Operating 12 5.1.2 Placing MG Set B In Service With MG Set A NOT Operating 15 5.2 Reset/Close

Reactor Trip Breakers..................................................................

18 6.0 NORMAL OPERATION 21 6.1 Placing MG Set A In Service With MG Set B Operating.........

21 6.2 Placing MG Set B In Service With MG Set A Operating 30 6.3 Manual Operation of Rod Control System Below 15 Percent Power................

39 6.4 Transferring

from Manual to Auto Rod Control.................................................

52 6.5 Transferring

from Auto to Manual Rod Control.................................................

53 7.0 SHUTDOWN.....................................................................................................

54 7.1 Removing the MG Set A From Service 54 7.2 Removing the MG Set B From Service 55

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 3 of 77 TABLE OF CONTENTS Page 2 of 2 Section Title Page 8.0 8.1 8.2 8.3

8.4 8.5 8.6 9.0 INFREQUENT

OPERATION.Alternate Method of Paralleling

MG Set A.Alternate Method of Paralleling

MG Set B.Resetting Step Counters After Withdrawing

Rods Above 231 Steps.Resetting Step Counters After Inserting Rods Below 0 Steps.Placing MG Set A In Service for Maintenance

.Placing MG Set B In Service for Maintenance

.RECORDS.56 56 58 60 61 62 69 76 SOURCE NOTES 77 ATTACHMENTS

ATTACHMENT

1: ATTACHMENT

2: CONTROL ROD DRIVE SYSTEM POWER CHECKLIST 1-85-1.01 CONTROL ROD DRIVE SYSTEM POWER CHECKLIST 2-85-1.01

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 4 of 77 1.0 INTRODUCTION

1.1 Purpose This instruction

provides the steps necessary for the operation of the Control Rod Drive System.1.2 Scope This instruction

provides detailed steps for the following operations:

Placing Control Rod Drive MG Sets in Service Removing Control Rod Drive MG Sets from Service Parallel Operation of Control Rod Drive MG Sets Manual Operation of the Control Rod Drive System Transferring

Rod Control from Manual to Auto Transferring

Rod Control from Auto to Manual 2.0 REFERENCES

2.1 Performance

References

A.Procedures

1.0-SI-NUC-000-038.0, Shutdown Margin 2.1 ,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts B.Tech Specs 1.3.4.1.2 C.Westinghouse

Tech.Bulletin NSD-TB-92-05RO

2.2 Developmental

References

A.Tech Specs 1.3.1.3.1 2.3.1.3.2 3.3.1.3.4 4.3.1.3.5 5.3.1.3.6

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 5 of 77 2.0 REFERENCES (Continued)

B.Technical Requirements

Manual 1.TR 3.1.3.3 C.F8AR 1.7.7.1.2.1 D.TVA Drawings 1.45N699-1 2.45N777-3 3.45N703-1, 2, 3,4 4.45N1646-4 5.45N2646-4 6.45N1624-1, 2, 3,4, 5, 8 7.45N2624-1, 2, 3,4, 5, 8 8.617F619

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 6 of 77 3.0 PRECAUTIONS

AND LIMITATIONS

A.Rod thermal lock-up is NOT a concern when the reactor trip breakers are OPEN.If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each.This will limit the possibility

of"thermalup" of the rods.This does not apply if performing

sections 8.5 or 8.6.B.If both MG sets are to be shutdown, the control rods and shutdown rods shall be inserted in the core and the reactor trip breakers OPEN prior to shutting down the MG sets.C.Reactor Trip Breakers shall NOT be closed while in Mode 3 unless in compliance

with LCO 3.4.1.2.D.Failure to perform 1 ,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts could result in the prevention

of AUTO SI if required.E.Under normal conditions, the control rod banks must be withdrawn and inserted in the prescribed

sequence.For withdrawal

the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, and Control Bank D.The insertion sequence is the reverse of the withdrawal

sequence.F.For manual bank sequencing, the prescribed

withdrawal

and insertion sequence should be followed.Rod motion of the correct bank should be monitored by observing the group step counters and the rod position indicators.

G.During Control Rod withdrawal, the Control Banks should be monitored for bank overlap.H.The control banks must be maintained

above their respective

insertion limits (Low-Low Alarm to ensure adequate shutdown in the event of a reactor trip, to ensure that maximum possible ejected rod reactivity

limits are maintained

and to ensure acceptable

core power distributions.

I.Before withdrawing

any rod bank from the fully inserted position, the group step counters and the rod position indicators

for that bank must be at zero steps.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 7 of 77 3.0 PRECAUTIONS

AND LIMITATIONS (Continued)

J.Deleted K.The Control Rods shall NOT be stepped or tripped unless the RCS pressure is at least 1 00 psig.L.RPls and step counters shall be maintained

within limits per TS 3.1.3.1 and 3.1.3.2.M.Continuous

rod motion shall comply with these restrictions:

CRDM OUTLET ROD MOTION LIMITS TEMPERATURE190°F 10 minutes ON 20 minutes OFF200°F 6 minutes ON 24 minutes OFF Time limitations

are due to a lower air flow rate of 48,000 cfm across the shroud combined with a higher temperature (Reference

TSIR-97-80P-30-636

and Westinghouse

Letters RIM's#838931005806, 838930920800, and 838931005803).

N.The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation

or indication:

1)Hand switch failure;2)relay failure, and 3)failure of both 100v DC power supplies (PS3 and PS6)simultaneously.

O.Defeating or restoring Tavg/Delta

T or NIS channel may cause step change in input to rod control.A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 8 of 77 3.0 PRECAUTIONS

AND LIMITATIONS (Continued)

P.Directional

Overcurrent

Relay Targets are reset by depressing

the Relay Target Reset Pushbutton

on the panel to break the target coil seal in circuit and then lifting the mechanical

reset at the bottom of the relay cover.Q.US/SRO Oversight for control rod manipulation

shall include:1.Prior to Rod Movement a.Ensure RPI's within T.S.range (+or-12 steps)b.Ensure delta flux will not be adversely affected c.Ensure Tavg and Rx Thermal power will not be adversely affected d.Verify on target with Rx Eng reactivity

balance sheet e.Verify power change will not exceed hourly rate f.Ensure no simultaneous

reactivity

manipulations

in progress (i.e.: borations, dilutions or turbine load changes)2.During Rod Movement a.Ensure RO has peer check b.Ensure RO is following procedure c.Ensure RO understands

how many steps they are moving rods d.Ensure RO has checked all the above mentioned items e.Watch performance

of rod manipulation

while listening to audible indication

of rod step f.Ensure peer check is doing their job g.Re-verify stepsa-d of initial evaluation

h.Ensure procedure is followed placing rods back to auto (Tavg-Tref mismatch)i.Monitor plant for expected response

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 9 of 77 UnitJ_4.0 PREREQUISITE

ACTIONS Date Q'Ix 7/987;NOTE Throughout

this instruction

where an IF/THEN statement occurs, the step may be N/A if the condition does NOT exist.[1]ENSURE the instruction

to be used is a copy of the effective version.[2]ENSURE Precautions

and Limitations, Section 3.0 has been reviewed.[3]ENSURE each performer documents their name and initials: WtA Print Name Initials W tJSoN'-r: A bbu+w7A[4]INDICATE below which performance

section of this instruction

will be used and the reason for this performance:

D 5.0 STARTUP/STANDBY

READINESS ff.6.0 NORMAL OPERATION D 7.0 SHUTDOWN D 8.0 INFREQUENT

OPERATION Reason: WI'1Hb/t4W

t3AN(P{LI\l(l To (2t A(:10 r'l s"1 A(l:1 U f

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 10 of 77 Unit Date_5.0 STARTUP/STANDBY

READINESS 5.1 Placing MG Set(s)in Standby Readiness[1]ENSURE Section 4.0, Prerequisites

complete.[2]ENSURE[HS-85-5110], Rod Control Mode Selector Switch is in the MANUAL position.[3]IF performance

is on Unit 1, THEN ENSURE Power Checklist 1-85-1.01 is complete.[4]IF performance

is on Unit 2, THEN ENSURE Power Checklist 2-85-1.01 is complete.NOTE Green targets on the breaker handswitches

can be obtained by rotating the operating switch to the TRIP position and releasing to the NEUTRAL position.[5]ENSURE the following breakers are in the required position: BREAKER REQUIRED TARGET INITIALS POSITION COLOR CRD MG SetA OPEN GREEN Motor Bkr 52A (480V Unit Bd)CRD MG Set B OPEN GREEN Motor Bkr 52B (480V Unit Bd)MG SetA OPEN GREEN Load (Generator)

Bkr 52-1 MG Set B OPEN GREEN Load (Generator)

Bkr 52-2[6]VERIFY[XA-55-4B-A5], ROD CONTROL MG SETS TRIPPED OR GROUNDED, alarm is NOT LIT.D D D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 11 of 77 UNIT Date_5.1 Placing MG Set(s)in Standby Readiness (Continued)

[7]TURN Generator No.1 Westinghouse

Thyrex Voltage Regulator (Reg)potentiometer

to the FULL COUNTER-CLOCKWISE

position and RETURN to the 9 O'CLOCK position.[8]TURN Generator No.2 Westinghouse

Thyrex Voltage Regulator (WTV Reg)potentiometer

to the FULL COUNTER-CLOCKWISE

position and RETURN to the 9 O'CLOCK position.[9]ENSURE the following MG Set handswitches

are in the required position: SWITCH REQUIRED INITIALS POSITION MG Set A Ammeter Selector Switch A MG Set B Ammeter Selector Switch A MG Set A Voltmeter Selector Switch AB MG Set B Voltmeter Selector Switch AB Generator No.1 Synchronize

Sel Sw OFF Generator No.2 Synchronize

Sel Sw OFF[10]ENSURE[1 KS], Three Pole Grounding Switch (located inside L-115 cabinet)is in the OPEN position.[11]ENSURE all relays and targets (located on L-115)for the MG Set breakers are RESET.End of Section 5.1

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 12 of 77 Unit Date----5.1.1 Placing MG Set A In Service With MG Set B Not Operating[1]ENSURE MG Set A is in Standby Readiness.

[2]START CRD MG Set A by placing[HS-85-1A]

MOTOR Breaker 52A Circuit Control in the CLOSE position.D D NOTE Allow 15 seconds for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.

[a]WHEN generator has increased to full speed, THEN[b]DEPRESS AND HOLD Gen Field Flash pushbutton.

[c]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.

[4]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with wrv Reg to a nominal 260 volts.D D D D NOTE Voltage may vary slightly between phases.[5]CHECK equal voltage on all phases using voltmeter selector switch.D NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[6]ENSURE MG Set A Load (GENERATOR)

Breaker 52-1[BCTF-85-121

is RACKED IN.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 13 of 77 Unit Date_5.1.1 Placing MG Set A In Service With MG Set B Not Operating (Continued)

[7]ENSURE MG Set B Load (GENERATOR)

Breaker 52-2[BCTF-85-22]

is RACKED IN.[8]ENSURE CRDM MG Set A Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al

(67 A)[1-RL Y-085-DE/4D/C]

(67C)[2-RLY-085-DG/4D/A]

(67 A)[2-RL Y-085-DG/4D/C]

(67C)[9]ENSURE targets for CRDM MG Set A Directional

Overcurrent

Relays RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]

(67 A)[1-RL Y-085-DE/4D/C]

(67C)[2-RL Y-085-DG/4D/A]

(67 A)[2-RL Y-085-DG/4D/C]

(67C)NOTE: Generator voltage will drop slightly as the electrical

load increases.

[10]CLOSE MG Set A Load (GENERATOR)

Breaker 52-1 USING[HS-85-121.

[11]IF MG Set A Load breaker 52-1 trips due to Directional

Overcurrent

Relay operation, THEN[a]RESET Directional

Overcurrent

Relays with Relay Target Reset Button on Relay panel.[b]RESET Directional

Overcurrent

Relay Targets.[c]RECLOSE MG Set A load Breaker 52-1 USING[HS-85-121.

D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 14 of 77 Unit Date_5.1.1 Placing MG Set A In Service With MG Set B Not Operating (Continued)

[d]IF another trip of breaker 52-1 occurs, REPEAT substeps[a],[b]and[c].[e]IF breaker 52-1 trips the third time, THEN NOTIFY SM and System Engineering

for assistance.

[12]WHEN placing the MG Sets in service initially OR Reactor Trip Breakers are to be reset, THEN GO TO Section 5.2, Resetting Reactor Trip Breakers.End of Section 5.1.1 D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 15 of 77 Date_Placing MG Set B In Service With MG Set A Not Operating Unit------5.1.2[1]ENSURE MG Set B is in Standby Readiness.

D[2]START CRD MG Set B by placing[HS-85-1 B]MOTOR Breaker 52B Circuit Control in the CLOSE position.D NOTE Allow 15 seconds for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.

D[4]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.

D[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.

D[5]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts.D NOTE Voltage may vary slightly between phases.[6]CHECK equal voltage on all phases using voltmeter selector switch.D NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[7]ENSURE MG Set A Load (GENERATOR)

Breaker 52-1 is RACKED IN.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 16 of 77 Unit Date_5.1.2 Placing MG Set B In Service With MG Set A Not Operating (Continued)

[8]ENSURE MG Set B Load (GENERATOR)

Breaker 52-2 is RACKED IN.[9]ENSURE CRDM MG Set B Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/A]

(67 A)[1-RLY-085-DF/3B/C]

(67C)[2-RL Y-085-DH/3B/A]

(67 A)[2-RL Y-085-DH/3B/C]

(67C)[10]ENSURE targets for CRDM MG Set B Directional

Overcurrent

Relays are RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al

(67 A)[1-RLY-085-DF/3B/C]

(67C)[2-RL Y-085-DH/3B/A]

(67 A)[2-RL Y-085-DH/3B/C]

(67C)NOTE Generator voltage will drop slightly as the electrical

load increases.

[11]CLOSE MG Set B Load (GENERATOR)

Breaker 52-2 USING[HS-85-22].

[12]IF MG Set B Load breaker 52-2 trips due to Directional

Overcurrent

Relay operation, THEN[a]RESET Directional

Overcurrent

Relays with Relay Target Reset Button on Relay panel.[b]RESET Directional

Overcurrent

Relay Targets.[c]RECLOSE MG Set B load Breaker 52-2 USING[HS-85-221.

D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 17 of 77 Unit Date_5.1.2 Placing MG Set B In Service With MG Set A Not Operating (Continued)

[d]IF another trip of breaker 52-2 occurs, REPEAT substeps[a],[b]and[c].[e]IF breaker 52-2 trips the third time, THEN NOTIFY SM and system engineering

for assistance.

[13]WHEN placing the MG Sets in service initially OR Reactor Trip Breakers are to be reset, THEN GO TO Section 5.2, Resetting Reactor Trip Breakers.End of Section 5.1.2 D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 18 of 77 unitl_5.2 Reset/Close

Reactor Trip Breakers[1]ENSURE desired MG Set is In Service.[2]ENSURE[1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED.(located in Panel L-115).[3]ENSURE lift coil disconnect

switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).[4]ENSURE all Control Rods and Shutdown Rods are inserted: ROD BANK FULLY INSERTED (-V)Shutdown Bank A[3'Shutdown Bank BShutdown Bank CShutdown Bank DControl Bank AControl Bank B CH'Control Bank CControl Bank DWTA W-rA CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[5]MOMENTARILY

PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY RPls and group step counters are at zero steps.W'tA

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 19 of 77 Unit Date 0#/oS/5.2 Reset/Close

Reactor Trip Breakers (Continued)

[6]ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT.BYPASS OPENRACKED OUT BREAKERBYA[}1'.-BYB cV cY[7]ENSURE Reactor Trip breakers are RACKED IN: TRIP BREAKER RTA RTB RACKED IN (..J)[8]ENSURE control power is ON by GREEN indicating

lights on M-4: BREAKER GREEN POSITION LIGHT INITIALS INDICATION

RTA ON UJ1tl RTB ON tAJflf[9]ENSURE Rod Control switch[HS-85-51111

is in MID position.[10]IF unit is in Mode 3,THEN ENSURE requirements

of Tech Spec 3.4.1.2 are met.[11]DEPRESS and HOLD FW Isol Reset pushbuttons

[HS-3-99A]

and[HS-3-99B].

[C.1]W10

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 20 of 77 I Unit------5.2 Reset/Close

Reactor Trip Breakers (Continued)

[12]IF resetting Unit 1 Reactor Trip Breakers, THEN CLOSE Rx Trip Breakers by placing[1-RT-1], in CLOSE position.[13]IF resetting Unit 2 Reactor Trip Breakers, THEN CLOSE Rx Trip Breakers by placing[2-HS-99-7], in CLOSE position.[14]VERIFY Reactor Trip Breakers CLOSED by RED indicating

lights on M-4: BREAKER POSITION RED LIGHT INITIALS INDICATION

RTA ON VV-rtt RTB ON W<1A[15]RELEASE FW Isol Reset push buttons[HS-3-99A]

and[HS-3-99B].

[C.1][16]NOTIFY IMs to perform 1,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts.[17]IF Shutdown or Control Rods will be withdrawn, THEN GO TO Section 6.3, Manual Operation of Rod Control System Below 15 Percent Power.End of Section 5.2 Date 0 J/xx,lo3

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 21 of 77 Unit Date----6.0 NORMAL OPERATION 6.1 Placing MG Set A In Service With MG Set B Operating[1]ENSURE MG Set B is In Service.[2]ENSURE MG Set A is in Standby Readiness.

D[3]ENSURE Reactor Trip Breakers are CLOSED.[4]START CRD MG Set A by placing[HS-85-1Al

MOTOR Breaker 52A Circuit Control in the CLOSE position.D[5]VERIFY generator speed increasing.

D[6]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.

D[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.

D NOTE Digital voltmeters

are much more accurate than panel meters and are the preferred instrumentation

when synchronizing

the generators.

The panel meters should only be used in the event of an emergency.

[7]REQUEST the SM/SRO to determine which of the following types of meters should be used to synchronize

and balance the MG Sets: MG Set panel meters.D Digital meters.D US/SRO

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 22 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

NOTE The auto synchronizing

circuit has a low voltage cutout circuit which will NOT allow the second MG Set to synchronize

if voltage on the loaded MG Set is less than 254 volts.Minimum voltage for placing the second generator in parallel is 260 volts.[8]IF using the MG Set panel voltmeters

for voltage adjustment, THEN[a]ENSURE MG Set B voltage is ADJUSTED with Westinghouse

Thyrex voltage (WTV)regulator potentiometer

to 260 volts (within plus or minus 1.0 volts)on panel meter.[b]ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer

to match MG Set B voltage.CAUTION Do NOT jar MG set panel doors when they are being opened or closed.There is a potential for inadvertent

relay operation.

[9]IF using digital meters for voltage adjustment, THEN[a]ENSURE qualified electrical

maintenance

personnel have OBTAINED 2 Fluke 8840A (or equivalent)

digital voltmeters

and 2 Keithley 197 (or equivalent)

digital voltmeters

to be used for synchronization

and balancing of the MG Sets.[b]ENSURE Keithley (or equivalent)

digital voltmeters (DVM)are CONNECTED to the terminals on the panel voltmeters

for both MG Set Band MG Set A.This DVM voltage is proportional

to generator voltage.[c]ENSURE Fluke (or equivalent)

digital voltmeters (DVM)are CONNECTED to the terminals on the panel ammeters for both MG Set Band MG Set A.This DVM voltage is proportional

to generator amps.(Step continued on Next Page)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 23 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

[9](Continued)

[d]ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer

to 108 volts (260 volts on panel meter)as indicated on the digital voltmeter, to be within plus or minus 1.0 volt (digital voltmeter).

[e]ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer

to match MG Set B voltage, to be within 0.5 volts (digital voltmeter).

[10]ENSURE CRDM MG Set A Directional

Overcurrent

Relay Target Coils RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]

(67 A)[1-RL Y-085-DE/4D/Cl

(67C)[2-RL Y-085-DG/4DI

A](67 A)[2-RL Y-085-DG/4D/Cl

(67C)[11]ENSURE targets for CRDM MG Set A Directional

Overcurrent

Relays RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al

(67 A)[1-RL Y-085-DE/4D/C]

(67C)[2-RL Y-085-DG/4D/A]

(67 A)[2-RL Y-085-DG/4D/C]

(67C)NOTE The following step should close the generator load breaker if paralleling

is successful.

[12]PLACE[HS-85-12Bl

Gen NO.1 SYNCHRONIZE

Switch in the ON position.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 24 of 77 Unit Date_6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

NOTE MG Set A should parallel within 17 seconds.[13]IF MG Sets are paralleled, THEN[a]PLACE[HS-85-12B]

Gen NO.1 SYNCHRONIZE

Switch in the OFF position.[14]IF DVMs are being utilized to balance generator amps (loading), THEN PERFORM the following to balance MG setA&B currents:[a]RECORD"as found" voltage and current readings: NOTE With MG sets paralleled, the voltmeters

are reading the same electrical

point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 25 of 77 Unit Date_6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

[14](Continued)

[a](Continued)

NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical

point.Therefore, data is required from 80TH MG sets in sub-steps7-12.7.ENSURE MG Set A and 8 Ammeter Selector Switches are selected for"A".8.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected tothepanel amp meters for: MG SetA mV------MG Set 8 mV 9.ENSURE MG Set A and 8 Ammeter Selector Switches are selected for"8".10.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set 8 mV 11.ENSURE MG Set A and 8 Voltmeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set 8 mV[b]EVALUATE'as found" data from Step[14][a]and the position of thedirectionalcontacts

on the Directional

Overcurrent

Relays (DaR)associated

with both MG sets to determine if any adjustment

is necessary.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 26 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

[14](Continued)

NOTE There are two methods by which balanced MG Set currents can be achieved using the WTV Voltage Potentiometers.

The preferred method is to balance the Directional

Overcurrent

Relaysdirectionalcontacts

to the far right and as steady as achievable

while maintaining

108+/-1 volts on the Fluke (or equivalent)

DVMs connected to the MG Set voltmeters.

This method will NOT usually result in currents balanced to within 1 mV (as read on the Keithley (or equivalent)).

The secondary method is to balance the Keithley (or equivalent)DVMsconnected

to the panel ammeters to within 1 mV while maintaining

108+/-1 volts as indicated by the Fluke (or equivalent)

DVM connected to the generator voltmeter.

[c]IF adjustment

is determined

to be necessary by Cognizant Craft or Engineer, THEN ADJUST WTV voltage regulator potentiometers

on MG SetsA&B to balance generator currents.[d]IF an adjustment

was made, THEN RECORD"as left" voltage and current readings: NOTE With MG sets paralleled, the voltmeters

are reading the same electrical

point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 27 of 77 Unit Date_6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

[14](Continued)

[d](Continued)

4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected tothepanel volt meters for: MG Set A OR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical

point.Therefore, data is required from BOTH MG sets in sub-steps7-12.7.ENSURE MG Set A and B Ammeter Selector Switches are selected for"A".8.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV 9.ENSURE MG Set A and B Ammeter Selector Switches are selected for"B".1 O.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 28 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

[14](Continued)

[d](Continued)

11.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV-----MG Set B mV[e]IF digital meters were installed in step[9], THEN 1.ENSURE all digital meters are removed.2.ENSURE the MG Set panel doors are closed.[15]IF MG Set A load breaker 52-1 closes but subsequently

trips due to Directional

Overcurrent

Relay operation, THEN[a]PLACE[HS-85-12Bl

Gen NO.1 SYNCHRONIZE

Switch in the OFF position.[b]ENSURE CRDM MG Set A Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al

(67 A)[1-RL Y-085-DE/4D/C]

(67C)[2-RLY-085-DG/4D/Al

(67 A)[2-RL Y-085-DG/4D/Cl

(67C)__I_-1st CV 1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 29 of 77 Unit Date----6.1 Placing MG Set A In Service With MG Set B Operating (Continued)

[c]ENSURE targets for CRDM MG Set A Directional

Overcurrent

Relays RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]

(67 A)[1-RL Y-085-DE/4D/Cl

(67C)[2-RLY-085-DG/4D/Al

(67 A)[2-RL Y-085-DG/4D/Cl

(67C)[d]IF 1 st attempt to synchronize, RETURN to step[12].[e]IF 2 nd attempt to synchronize

was unsuccessful, THEN INITIATE a WO to troubleshoot

the problem.[16]IF MG Set A does NOT parallel within 17 seconds, THEN[a]CHECK MG Set voltages.[b]IF voltages appear to have drifted apart AND/OR another adjustment

is desired, THEN D D D 1.2.PLACE[HS-85-12Bl

Gen No.1 SYNCHRONIZE

Switch in the OFF position.RETURN to step[7].D D[17]IF Alternate Method of Paralleling

MG Set A is desired, THEN GO TO Section 8.1.[18]ENSURE target for CRD MG Set A Load (GENERATOR)

Bkr 52-1 is RED by placing[HS-85-121

GENERATOR breaker circuit control in the CLOSE position.End of Section 6.1 D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 30 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating[1]ENSURE MG Set A is In Service.D[2]ENSURE MG Set B is in Standby Readiness.

D[3]ENSURE Reactor Trip Breakers are CLOSED.D[4]ST ART CRD MG Set B by placing fHS-85-1 B]MOTOR Breaker 52B Circuit Control in the CLOSE position.D[5]VERIFY generator speed increasing.

D[6]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.

D[b]WHEN voltage is greater than 250 volts, THEN RELEASE Gen Field Flash pushbutton.

D NOTE Digital voltmeters

are much more accurate than panel meters and are the preferred instrumentation

when synchronizing

the generators.

The panel meters should only be used in the event of an emergency.

[7]REQUEST the SM/SRO to determine which of the following types of meters should be used to synchronize

and balance the MG Sets: MG Set panel meters.D Digital meters.D SM/SRO

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2.Rev 32 Page 31 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

NOTE The auto synchronizing

circuit has a low voltage cutout circuit which will NOT allow the second MG Set to synchronize

if voltage on the loaded MG Set is less than 254 volts.Minimum voltage for placing the second generator in parallel is 260 volts.[8]IF using the MG Set panel voltmeters

for voltage adjustment, THEN[a]ENSURE MG Set A voltage is ADJUSTED with Westinghouse

Thyrex voltage (WTV)regulator potentiometer

to 260 volts (within plus or minus 1.0 volts)on panel meter.[b]ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer

to match MG Set A voltage.CAUTION Do NOT jar MG set panel doors when they are being opened or closed.There is a potential for inadvertent

relay operation.

[9]IF using digital meters for voltage adjustment, THEN[a]ENSURE qualified electrical

maintenance

personnel have OBTAINED 2 Fluke 8840A (or equivalent)

digital voltmeters

and 2 Keithley 197 (or equivalent)

digital voltmeters

to be used for synchronization

and balancing of the MG Sets.[b]ENSURE Keithley (or equivalent)

digital voltmeters (DVM)are CONNECTED to the terminals on the panel voltmeters

for both MG Set Band MG Set A.This DVM voltage is proportional

to generator voltage.[c]ENSURE Fluke (or equivalent)

digital voltmeters (DVM)are CONNECTED to the terminals on the panel ammeters for both MG Set Band MG Set A.This DVM voltage is proportional

to generator amps.(Step continued on Next Page)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 32 of 77 Unit Date_6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[d]ENSURE MG Set A voltage is ADJUSTED with WTV regulator potentiometer

to 108 volts (260 volts on panel meter)as indicated on the digital voltmeter, to be within plus or minus 1.0 volt (DVM).[e]ENSURE MG Set B voltage is ADJUSTED with WTV regulator potentiometer

to match MG Set A voltage, to be within 0.5 volts (DVM).[10]ENSURE CRDM MG Set B Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/A]

(67 A)[1-RLY-085-DF/3B/C]

(67C)[2-RL Y-085-DH/3B/Al

(67 A)[2-RL Y-085-DH/3B/Cl

(67C)re ay.o er nl Relay INITIALS[1-RL Y-085-DF/3B/Al

(67 A)[1-RLY-085-DF/3B/Cl

(67C)[2-RL Y-085-DH/3B/Al

(67 A)[2-RL Y-085-DH/3B/Cl

(67C)[11]ENSURE targets for CRDM MG Set B Directional

Overcurrent

Relays are RESET (Mechanical

Linkage onI)(N/A th U't)NOTE The followingstepshould

close the generator load breaker if paralleling

is successful.

[12]PLACE[HS-85-22B]

Gen NO.2 SYNCHRONIZE

Switch in the ON position.NOTE MG Set B should parallel within 17 seconds.[13]IF MG Sets are paralleled, THEN[a]PLACE[HS-85-22B]

Gen NO.2 SYNCHRONIZE

Switch in the OFF position.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 33 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[14]IF DVMs are being utilized to balance generator amps (loading), THEN PERFORM the following to balance MG setA&B currents:[a]RECORD"as found" voltage and current readings: NOTE With MG sets paralleled, the voltmeters

are reading the same electrical

point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORDoneMG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG SetAOR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORDoneMG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG SetAOR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical

point.Therefore, data is required from BOTH MG sets in sub-steps7-12.7.ENSURE MG Set A and B Ammeter Selector Switches are selected for"A".

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 34 of 77 Unit Date_6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[14](Continued)

[a](Continued)

8.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected tothepanel amp meters for: MG SetA mV------MG Set B mV 9.ENSURE MG Set A and B Ammeter Selector Switches are selected for"B".1 O.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV 11.ENSURE MG Set A and B Ammeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV[b]EVALUATE'as found" data from Step[14][a]and the position of the directional

contacts on the Directional

Overcurrent

Relays (DOR)associated

with both MG sets to determine if any adjustment

is necessary.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 35 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[14](Continued)

NOTE There are two methods by which balanced MG Set currents can be achieved using the WTV Voltage Potentiometers.

The preferred method is to balance the Directional

Overcurrent

Relays directional

contacts to the far right and as steady as achievable

while maintaining

108+/-2 volts on the Fluke (or equivalent)

DVMs connected to the MG Set voltmeters.

This method will NOT usually result in currents balanced to within 1 mV (as read on the Keithley (or equivalent)).

The secondary method is to balance the Keithley (or equivalent)

DVMs connected to the panel ammeters to within 1 mV while maintaining

108+/-1 volts as indicated by the Fluke (or equivalent)

DVM connected to the generator voltmeter.

[c]IF adjustment

is determined

to be necessary by Cognizant Craft or Engineer, THEN ADJUST WTV voltage regulator potentiometers

on MG SetsA&B to balance generator currents.[d]IF an adjustment

was made, THEN RECORD"as left" voltage and current readings: NOTE With MG sets paralleled, the voltmeters

are reading the same electrical

point.Therefore, data is only required from one MG set in sub-steps 1-6.1.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"AB".2.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 3.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"BC".

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 36 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[14](Continued)

[d](Continued)

4.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts 5.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"CA".6.RECORD one MG Set Output voltage as indicated by the Keithley (or equivalent)

DVM connected to the panel volt meters for: MG Set A OR MG Set B volts NOTE With MG sets paralleled, the ammeters are NOT reading the same electrical

point.Therefore, data is required from BOTH MG sets in sub-steps7-12.7.ENSURE MG Set A and B Ammeter Selector Switches are selected for"A".8.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV 9.ENSURE MG Set A and B Ammeter Selector Switches are selected for"B".10.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV------MG Set B mV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 37 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[14](Continued)

[d](Continued)

11.ENSURE MG Set A and B Voltmeter Selector Switches are selected for"C".12.RECORD output current as indicated by the Fluke (or equivalent)

DVM connected to the panel amp meters for: MG SetA mV-----MG Set B mV[e]IF digital meters were installed instep[9], THEN 1.ENSURE all digital meters are removed.__I_-1st CV 2.ENSURE the MG Set panel doors are closed.[15]IF MG Set B load breaker 52-2 closes but subsequently

trips due to Directional

Overcurrent

Relay operation, THEN[a]PLACE[HS-85-22Bl

Gen NO.2 SYNCHRONIZE

Switch in the OFF position.[b]ENSURE CRDM MG Set B Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al

(67 A)[1-RLY-085-DF/3B/C]

(67C)[2-RL Y-085-DH/3B/Al

(67 A)[2-RL Y-085-DH/3B/C]

(67C)1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 38 of 77 Unit Date----6.2 Placing MG Set B In Service With MG Set A Operating (Continued)

[c]ENSURE targets for CRDM MG Set B Directional

Overcurrent

Relays are RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al

(67 A)[1-RLY-085-DF/3B/Cl

(67C)[2-RL Y-085-DH/3B/Al

(67 A)[2-RL Y-085-DH/3B/Cl

(67C),[d]IF 1 st attempt to synchronize, RETURN to step[12].[e]IF 2 nd attempt to re-synchronize

was unsuccessful, THEN INITIATE a WO to troubleshoot

the problem.[16]IF MG Set B does NOT parallel within 17 seconds, THEN[a]CHECK MG Set voltages.[b]IF voltages appear to have drifted apart AND/OR another adjustment

is desired, THEN 1.PLACE[HS-85-22Bl

Gen NO.2 SYNCHRONIZE

Switch in the OFF position.2.RETURN to step[7].[17]IF Alternate Method of Paralleling

MG Set B is desired, THEN GO TO Section 8.2.[18]ENSURE target for CRD MG Set B Load (GENERATOR)

Bkr 52-2 is RED by placing[HS-85-22]

GENERATOR breaker circuit control in the CLOSE position.End of Section 6.2 D D D D D D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 39 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power CAUTION If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each.This will limit the possibility

of"thermal lock-up" of the rods.Thermal lock-up is NOT a concern during unit heatup.NOTE Continuous

rod motion shall comply with these restrictions:

CRDM OUTLET ROD MOTION LIMITS TEMPERATURE

s190°F 10 minutes ON 20 minutes OFF s200°F 6 minutes ON 24 minutes OFF[1]ENSURE Section 5.2, ReseUClose

Reactor Trip Breakers has been completed.

[2]IF the shutdown and control rods were withdrawn 5 steps to prevent thermal lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawal.

D 1st CV NOTE CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)Resets: A.All GROUP STEP COUNTERS on the Control Board.B.The master cycler reversible

counter.C.All slave cycler counters.D.The bank overlap counter.E.All internal memory and alarm circuits.F.All pulse-to-analog

converters

in the Rod Position Indication

System.ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[3]MOMENTARILY

PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System.D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 40 of 77 Unit Oate_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

CAUTION Before withdrawing

any rod from the fully inserted position, all Group Step Counters and all Rod Position indicators

must be at zero steps.[4]ENSURE all Full Length Rod step counters reset to zero.[5]VERIFY rod control IN-OUT direction lights are NOT LIT.[6]DEPRESS[RCAS], Rod Urgent Failure Alarm Reset.[7]RESET Window 6 (A-6), ROD CONTROL SYSTEM URGENT FAILURE alarm on panel[XA-55-4Bl

using[XS-55-4A], Annunciator

RESET/ACKITEST

Switch.[8]VERIFY the following rod control system alarms on panel[XA-55-4Bl

are NOT LIT: WINDOW NOT LIT NUMBER N)5 (A5)D 6 (A6)D 11 (84)D 12 (85)D 13(86)D 18 (C4)D 19(C5)D 27 (06)D 34 (E6)D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 41 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

[9]ENSURE Plant computer points for rod bank position are ZERO using the following computer points: COMPUTER PT ROD BANK..J U0049 Control A D U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D U0056 Shutdown D D[10]MONITOR Control Rod position USING Rod Position Indicators

ICS screen 30 minute trend during SD&Control Banks withdrawal

to aid in detecting rod misalignment.

D[11]IF Individual

Rod Position Indication

does not indicate proper rod position during withdrawal

of SD Banks, THEN[a]STOP rod withdrawal.

D[b]ENSURE subcriticality.

D[c]CONTACT MIG AND INITIATE troubleshooting.

D[d]IF troubleshooting

does not resolve the problem, OR subcriticality

can NOT be verified, THEN INITIATE Reactor TRIP.D[12]IF Individual

Rod Position Indication

does not indicate proper rod position during withdrawal

of Control Banks, THEN GO TO AOP-C.01 section 2.6 Rod Position Indicator (RPI)Malfunction

-Modes 1 or 2.D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 42 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

CAUTION NOTE 1 Under normal conditions

control rod banks must be withdrawn and inserted in the prescribed

sequence.For withdrawal, the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank 0, Control Bank A, Control Bank B, Control Bank C, Control Bank D.The insertion sequence is the reverse of the withdrawal

sequence.Startup rate, Source range, Intermediate

range, Nuclear Instrumentation

recorders, Group Step Counters and the Rod Position Indicators

should be monitored during each bank withdrawal.

NOTE 2 The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation

or indication:

1)Hand switch failure;2)relay failure, and 3)simultaneous

failure of both 100v DC power supplies (PS3 and PS6)[13]PLACE[HS-85-511

0], Rod Control Mode Selector to the SBA position.1st CV[14]VERIFY Rod Speed Indicator[SI-412], indicates 64 Steps/minute.

1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 43 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

NOTE Monitor Group Step Counters, Rod Position Indicator and the"IN-OUT" status lights to ensure anticipated

motion as each bank is being withdrawn.

Rod speed indicator should be reading 64 steps per minute.[15]ENSURE Shutdown Bank A demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Shutdown Bank A one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111

to withdraw Shutdown Bank A one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank A fully INSERTED.D 2.RETURN to beginning of this step.D NOTE The fully withdrawn position for shutdown and control rods is defined by TI-28, Att.6.[16]WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN position using[HS-85-5111].

1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 44 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

[17]PLACE[HS-85-511

01, Rod Control Mode Selector to the SBB position.1st CV[18]VERIFY Rod Speed Indicator[SI-412], indicates 64 Steps/minute.

__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation

or indication:

1)Hand switch failure;2)relay failure, and 3)simultaneous

failure of both 100v DC power supplies (PS3 and PS6).[19]ENSURE Shutdown Bank B demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Shutdown Bank B one-half step at a time, for one full step.1 st cv[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-5111]

to withdraw Shutdown Bank B one-half step at a time, for the second full step.1st cv[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank B fully INSERTED and D 2.RETURN to beginning of this step.D[20]WITHDRAW Shutdown Bank B to the FULL Y WITHDRAWN position using[HS-85-5111].

1st cv

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 45 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

[21]PLACE[HS-85-511

0], Rod Control Mode Selector to the SBC position.1st CV[22]VERIFY Rod Speed Indicator[SI-412], indicates o Steps/minute.

__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation

or indication:

1)Hand switch failure;2)relay failure, and 3)simultaneous

failure of both 100v DC power supplies (PS3 and PS6).[23]ENSURE Shutdown Bank C demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Shutdown Bank C one full step.1st CV[b]CHECK group demand position counter advances properly.D[c]BUMP[HS-85-5111]

to withdraw Shutdown Bank C a second full step.1st CV[d]VERIFY group demand position counter advanced properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank C fully INSERTED and D 2.RETURN to beginning of this step.D[24]WITHDRAW Shutdown Bank C to the FULLY WITHDRAWN position using[HS-85-51111.

1 st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 46 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

[25]PLACE[HS-85-511

0], Rod Control Mode Selector to the SBD position.1st CV[26]VERIFY Rod Speed Indicator[SI-412], indicates o Steps/minute.

__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation

or indication:

1)Hand switch failure;2)relay failure, and 3)simultaneous

failure of both 100v DC power supplies (PS3 and PS6).[27]ENSURE Shutdown Bank D demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Shutdown Bank D one full step.1 st CV[b]CHECK group demand position counter advances properly.D[c]BUMP[HS-85-51111

to withdraw Shutdown Bank D a second full step.1st CV[d]VERIFY group demand position counter advanced properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Shutdown Bank D fully INSERTED and D 2.RETURN to beginning of this step.D[28]WITHDRAW Shutdown Bank D to the FULL Y WITHDRAWN position using[HS-85-5111

1.1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 47 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

NOTE Remainder of this section performed in conjunction

with 0-GO-2 or 0-RT-NUC-000-003.0.

[29]PLACE[HS-85-511

0], Rod Control Mode Selector to the MANUAL position.1st CV[30]VERIFY Rod Speed Indicator[SI-412], indicates 48 Steps/minute.

__I_-1st CV NOTE The following failures will render the rod control system incapable of automatic and/or manual motion without any annunciation

or indication:

1)Hand switch failure;2)relay failure, and 3)simultaneous

failure of both 100v DC power supplies (PS3 and PS6).[31]ENSURE Control Bank A demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Control Bank A one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-5111]

to withdraw Control Bank A one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank A fully INSERTED and D 2.RETURN to beginning of this step.D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 48 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

[32]CONTINUE withdrawal

of Control Bank A using[HS-85-5111], Rod Control Switch to 128 steps or next doubling.NOTE When Control Bank A is above 20 steps, alarm FULL LENGTH RODS AT BOTTOM light on[XA-55-4B]

should clear.When Control Bank A gets above 20 steps and rods are driven back in, the alarm will come back in.When Control Banks B, C, and 0 get above 35 steps, then drop below 20 steps, the alarm will come back in.[33]WHEN Control Bank A is above 20 steps, THEN ENSURE Window 28 (0-7), FULL LENGTH RODS RODS AT BOTTOM alarm on panel[XA-55-4B]

CLEARS.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 49 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

CAUTION When Control Bank A is reaches 128 steps, Control Bank B should begin to move.Each successive

bank should begin to move when the previous bank reaches 128 steps.[34]WHEN Control Bank A is withdrawn to 128 steps, THEN ENSURE Control Bank B demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Control Bank B one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111

to withdraw Control Bank B one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank B fully INSERTED and D 2.RETURN to beginning of this step.D[35]CONTINUE withdrawal

of Control Bank Busing[HS-85-5111l

to 128 steps or next doubling.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 50 of 77 Unit Date_6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

[36]WHEN Control Bank B is withdrawn to 128 steps, THEN ENSURE Control Bank C dema,nd position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-51111, Rod Control Switch to withdraw Control Bank C one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111

to withdraw Control Bank C one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank C fully INSERTED and D 2.RETURN to beginning of this step.D[37]CONTINUE withdrawal

of Control Bank C using[HS-85-51111

to 128 steps or next doubling.NOTE Three steps are added to the low-low insertion limit (110 steps@zero power)until LEFM is available.

[38]WHEN Control Bank C is113 Steps, THEN ENSURE Window 14 (B-7), ROD CONTROL BANKS LIMIT LOW-LOW alarm on panel[XA-55-4Bl

CLEARS.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 51 of 77 Unit Date----6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)

NOTE Three steps are added to the low insertion limit (120 steps@zero power)until LEFM is available.

[39]WHEN Control Bank C is123 steps, THEN ENSURE Window 7 (A-7), ROD CONTROL BANKS LIMIT LOW alarm on panel[XA-55-4Bl

CLEARS.[40]WHEN Control Bank C is withdrawn to 128 steps, THEN ENSURE Control Bank 0 demand position counters operational

by performing

the following:

[C.2][a]BUMP[HS-85-5111], Rod Control Switch to withdraw Control Bank 0 one-half step at a time, for one full step.1st CV[b]CHECK group demand position counters advance properly.D[c]BUMP[HS-85-51111

to withdraw Control Bank 0 one-half step at a time, for the second full step.1st CV[d]VERIFY group demand position counters advance properly.D[e]IF group demand position counters do NOT advance properly, THEN A.STOP rod withdrawal.

D B.INITIATE WO to have counter repaired.D C.WHEN counter is repaired, THEN 1.ENSURE Control Bank D fully INSERTED and D 2.RETURN to beginning of this step.D[41]CONTINUE withdrawal

of Control Bank Dusing[HS-85-51111

to next doubling or criticality.

End of Section 6.3

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 52 of 77 Unit Date----6.4 Transferring

from Manual to Auto Rod Control NOTE 1 NOTE 2 NOTE 3 A laminated copy of this section can be maintained

in the Unit Control Room for repetitive

use for routine rod manipulations.

Defeating or restoring Tavg/Delta

T or NIS channel may cause step change in input to rod control.A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.This Section may be N/A if Rod Control is being returned to AUTO in response to a transient (runback)condition.

[1]ENSURE turbine power is greater than 15 percent.[2]ENSURE Window 31 (E-3), LOW TURB IMPULSE PRESS ROD WITHDRAWAL

BLOCKED C-5, Permissive

light on panel[XA-55-4A]

is NOT LIT.[3]ENSURE lessthan1 degree Tavg/Tref mismatch.[4]PLACE[HS-85-511

0], Rod Control Mode Selector in the AUTO position.1st cv[5]VERIFY Rod Speed Indicator[SI-412], indicates 8 Steps/minute.

1 st CV End of Section 6.4

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 53 of 77 Unit Date_6.5 Transferring

from Auto to Manual Rod Control NOTE 1 A laminated copy of this section can be maintained

in the Unit Control Room for repetitive

use for routine rod manipulations.

NOTE 2 Manual rod withdrawal

is inhibited by any of the following signals: A.C-1, High Flux Intermediate

Range Monitor B.C-2, High Flux Power Range Monitor C.C-3, Overtemperature

Delta-T D.C-4, Overpower Delta-T[1]PLACE[HS-85-5110], Rod Control Mode Selector in the MANUAL position.[2]VERIFY Rod Speed Indicator[SI-412], indicates 48 Steps/minute.

[3]IF control rod movement is required, THEN ADJUST position using[HS-85-5111], Rod Control Switch.[4]IF it is desired to leave[HS-85-5110], Rod Control Mode Selector in Manual for an extended period of time, THEN PLACE this Section in the Active Procedures

Book.[5]WHEN it is desired to place[HS-85-5110], Rod Control Mode Selector to Automatic, THEN GO TO Section 6.4.End of Section 6.5 1st CV 1st CV 1st CV

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 54 of 77 Unit Date----7.0 SHUTDOWN 7.1 Removing the MG Set A From Service[1]IF MG Set B has been removed from service, THEN[a]ENSURE the control rods and shutdown rods are fully inserted into the core.NOTE: The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional

Overcurrent

Relay contacts.[b]IF the reactor trip breakers are CLOSED THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99A]

and[HS-3-99B]

2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset Pushbuttons

[HS-3-99Al

and[HS-3-99B]

CAUTION Opening GENERATOR or MOTOR breaker of an MG Set that is to remain in service will result in a reactor trip.[2]OPEN MG Set A Load (GENERATOR)

Breaker 52-1 USING[HS-85-121.

D NOTE Voltage will be maintained

for a short time after opening the motor circuit breaker due to an intended time delay.[3]STOP CRD MG Set A by placing MOTOR Breaker 52A Circuit Control in the TRIP position USING[HS-85-1A].

[4]VERIFY MG Set A speed decreases.

End of Section 7.1 D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 55 of 77 Unit Date----7.2 Removing the MG Set B From Service[1]IF MG Set A has been removed from service, THEN[a]ENSURE the control rods and shutdown rods are fully inserted into the core.NOTE: The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional

Overcurrent

Relay contacts.[b]IF the reactor trip breakers are CLOSED THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99A]

and[HS-3-99Bl

2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset pushbuttons

[HS-3-99A]

and[HS-3-99Bl.

CAUTION Opening GENERATOR or MOTOR breaker of an MG Set that is to remain in service will result in a reactor trip.[2]OPEN MG Set B Load (GENERATOR)

Breaker 52-2 USING[HS-85-221.

D NOTE Voltage will be maintained

for a short time after opening the motor circuit breaker due to an intended time delay.[3]STOP CRD MG Set B by placing MOTOR Breaker 52B Circuit Control in the TRIP position USING[HS-85-1 B].[4]VERIFY MG Set B speed decreases.

End of Section 7.2 D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 56 of 77 Unit Date----8.0 INFREQUENT

OPERATION 8.1 Alternate Method of Paralleling

MG Set A CAUTION This method should only be used if one unit is on line and providing for a load that may cause too great a speed difference

to synchronize, and parallel operation is deemed necessary.

[1]OBTAIN Shift Manager's approval to perform this method of paralleling

MG Set A.//SM/SRO[2]ENSURE Section 6.1 has been completed.

[3]ENSURE CRDM MG Set A Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al

(67 A)[1-RL Y-085-DE/4D/Cl

(67C)[2-RLY-085-DG/4D/A]

(67A)[2-RL Y-085-DG/4D/Cl

(67C)[4]ENSURE targets for CRDM MG Set A Directional

Overcurrent

Relays are RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/Al

(67 A)[1-RLY-085-DE/4D/C]

(67C)[2-RL Y-085-DG/4D/A]

(67 A)[2-RL Y-085-DG/4D/Cl

(67C)[5]PLACE CRD MG Set A MOTOR Breaker 52A Circuit Control[HS-85-1Al

in the TRIP position.[6]VERIFY MG Set A speed decreases.

Date Time D D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 57 of 77 Unit Date----8.1 Alternate Method of Paralleling

MG Set A (Continued)

[7]IF MG Sets are paralleled, THEN[a]PLACE Gen No.1 SYNCHRONIZE

Switch[HS-85-12B]

in the OFF position.D[b]ENSURE target for CRD MG Set A Mtr Bkr 52A is RED by placing the MOTOR breaker circuit control[HS-85-1Al

in the CLOSE position.D[c]IF digital meters were used in Section 6.1, THEN A.ENSURE all digital meters are removed.__/__1st CV B.'ENSURE the MG Set panel doors are closed.1st CV[d]ENSURE target for CRD MG Set A Load (GENERATOR)

Bkr 52-1 is RED by placing the GENERATOR breaker circuit control in the CLOSE position.D[8]IF MG Set A does NOT parallel, THEN REPEAT Section 6.1 as required to synchronize

MG Sets.[9]CHECK all Power, Logic, and Hold cabinets for alarm lights.End of Section 8.1 D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 58 of 77 Unit Date_8.2 Alternate Method of Paralleling

MG Set B CAUTION This method should only be used if one unit is on line and providing for a load that may cause too great a speed difference

to synch, and parallel operation is deemed necessary.

[1]OBTAIN Shift Manager's approval to perform this method of paralleling

MG Set B.SM/SRO[2]ENSURE Section 6.2 has been completed.

[3]ENSURE CRDM MG Set B Directional

Overcurrent

Relay Target Coils are RESET (Panel(N/A other Unit)Relay INITIALS[1-RLY-085-DF/3B/A]

(67A)[1-RLY-085-DF/3B/C]

(67C)[2-RL Y-085-DH/3B/Al

(67 A)[2-RL Y-085-DH/3B/Cl

(67C)[4]ENSURE targets for CRDM MG Set B Directional

Overcurrent

Relays are RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/Al

(67 A)[1-RLY-085-DF/3B/C]

(67C)[2-RL Y-085-DH/3B/Al

(67 A)[2-RL Y-085-DH/3B/Cl

(67C)[5]PLACE CRD MG Set B MOTOR Breaker 528 Circuit Control[HS-85-1 B]in the TRIP position.[6]VERIFY MG Set 8 speed decreases.//Date Time D D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 59 of 77 Unit Date----8.2 Alternate Method of Paralleling

MG Set B (Continued)

[7]IF MG Sets are paralleled, THEN[a]PLACE[HS-85-22Bl

Gen NO.2 SYNCHRONIZE

Switch in the OFF position.[b]ENSURE target for CRD MG Set B Mtr Bkr 52B is RED by placing the MOTOR breaker circuit control[HS-85-1 B]in the CLOSE position.[c]IF digital meters were used in section 6.2, THEN 1.ENSURE all digital meters are removed.2.ENSURE the MG Set panel doors are closed.D D__I_-1st CV 1st CV[d]ENSURE target for CRD MG Set B Load (GENERATOR)

Bkr 52-2 is RED by placing the GENERATOR breaker circuit control in the CLOSE position.D[8]IF MG Set B does NOT parallel, THEN REPEAT Section 6.2 as required to synchronize

MG Sets.[9]CHECK all Power, Logic, and Hold cabinets for alarm lights.End of Section 8.2 D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 60 of 77 Unit Date_8.3 Resetting Step Counters After Withdrawing

Rods Above 231 StepsRamp Up ButtonStep Down ButtonReset to Zero LCD Step Counter[1]DEPRESS the affected group step counter"Step Down Button" to obtain 231 on display.[2]IF the affected bank is a control bank, THEN NOTIFY IMs to:[a]UPDATE the Pulse-to-Analog

converter.

[b]CHECK the bank overlap unit in the logic cabinet.[c]CHECK Master Cycler and UPDATE as needed.[3]ENSURE Plant computer points for rod bank position are UPDATED usingthefollowing

computer points: COMPUTER PT ROD BANKU0049 Control A D U0050 Control B D U0051 Control C D U0052 Control D D U0053 Shutdown A D U0054 Shutdown B D U0055 Shutdown C D UOO56 Shutdown D D End of Section 8.3 D D D

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 61 of 77 Unit Date----8.4 Resetting Step Counters After Inserting Rods Below 0 StepsRamp Up ButtonStep Down ButtonReset to Zero LCD Step Counter NOTE Depressing

the"Ramp Up Button" will cause a rapid change in the display.[1]MOMENTARILY

DEPRESS the affected group step counter"Ramp Up Button" to obtain 0 on display.[2]IF the affected bank is a control bank, THEN NOTIFY IMs to:[a]UPDATE the Pulse-to-Analog

converter.

D[b]CHECK the bank overlap unit in the logic cabinet.D[c]CHECK Master Cycler and UPDATE as needed.D[3]ENSURE Plant computer points for rod bank position are UPDATED using the following computer points: COMPUTER PT ROD BANKUOO49 Control A D U0050 Control B D UOO51 Control C D UOO52 Control D D UOO53 Shutdown A D UOO54 Shutdown B D UOO55 Shutdown C D U0056 Shutdown D D End of Section 8.4

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 62 of 77 Unit Date----8.5 Placing MG Set A In Service for Maintenance

[1]ENSURE clearance in place to isolate power to Rod Control coils on reactor head AND RECORD Hold Order Number.------[2]START CRD MG Set A by placing[HS-85-1Al

MOTOR Breaker 52A Circuit Control in the CLOSE position.NOTE Allow 15 seconds for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.

[4]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.

[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.

[5]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts.NOTE Voltage may vary slightly between phases.[6]CHECK voltage approximately

equal on all phases using voltmeter selector switch.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 63 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenance(Continued)

[7]WHEN Maintenance

requires MG Set A Load Breaker to be closed, THEN PERFORM the following:

NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[a]ENSURE MG Set A Load (GENERATOR)

Breaker 52-1[BCTF-85-121

is RACKED IN.[b]ENSURE MG Set B Load (GENERATOR)

Breaker 52-2[BCTF-85-221

is RACKED IN.[c]ENSURE CRDM MG Set A Directional

Overcurrent

Relay Target Coils are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4D/A]

(67 A)[1-RLY-085-DE/4D/Cl

(67C)[2-RL Y-085-DG/4D/Al

(67 A)[2-RL Y-085-DG/4D/Cl

(67C)[d]ENSURE targets for CRDM MG Set A

Overcurrent

Relays are RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RL Y-085-DE/4DI

Al (67 A)[1-RL Y-085-DE/4D/C]

(67C)[2-RLY-085-DG/4D/Al

(67 A)[2-RL Y-085-DG/4D/Cl

(67C)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 64 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenanee(Continued)

NOTE Generator voltage will drop slightly as the electrical

load increases.

[e]CLOSE MG Set A Load (GENERATOR)

Breaker 52-1 USING[HS-85-12].

[f]IF MG Set A Load breaker 52-1 trips due to Directional

Overcurrent

Relay operation, THEN[1]RESET Directional

Overcurrent

Relays with Relay Target Reset Button on Relay panel.[2]RESET Directional

Overcurrent

Relay Targets.[3]RECLOSE MG Set A load Breaker 52-1 USING[HS-85-12].

[4]IF another trip of breaker 52-1 occurs, THEN REPEAT substeps[a],[b]and[e].[5]IF breaker 52-1 trips the third time, THEN NOTIFY SM and System Engineering

for assistance.

[8]WHEN MAINTENANCE

requires reactor trip/bypass

breakers to be closed, THEN PERFORM the following:

[a]ENSURE[1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED.(located in Panel L-115).[b]ENSURE lift coil disconnect

switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 65 of 77 Unit Date_8.5 Plac-ing MG Set A In Service for Maintenance(Continued)

CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[c]MOMENTARILY

PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY group step counters are at zero steps.[d]ENSURE Reactor Trip Bypass breakers are in required alignment per Maintenance

Procedure:

BYPASS RACKED IN RACKED OUT BREAKERBYA D D BYB D D[e]ENSURE Reactor Trip breakers are in required alignment per Maintenance

Procedure:

TRIP RACKED IN RACKED OUT BREAKERRTA D D RTB D D[f]ENSURE control power is ON by GREEN indicating

lights on M-4: (NA breakers not racked in)BREAKER GREEN INITIALS LIGHT RTA ON RTB ON BYA ON BYB ON

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 66 of 77 Unit Date----8.5 Placing MG Set A In Service for Maintenance(Continued)

[g]ENSURE Rod Control switch[HS-85-5111]

is in MID position.[h]IF unit is in Mode 3,THEN ENSURE requirements

of Tech Spec 3.4.1.2 are met.[i]DEPRESS and HOLD FW Isol Reset push buttons[HS-3-99Al

and[HS-3-99Bl.[C.1]

U]IF maintenance

being performed on Unit 1, THEN CLOSE Rx Trip Breakers by placing[1-RT-11, to CLOSE position.[k]IF maintenance

being performed on Unit 2, THEN CLOSE Rx Trip Breakers by placing[2-HS-99-7], to CLOSE position.[I]VERIFY Reactor Trip Breakers/Reactor

Trip Bypass breakers CLOSED by RED indicating

lights on M-4: (NA breakers not closed)BREAKER RED LIGHT INITIALS RTA ON RTB ON BYA ON BYB ON[m]RELEASE FW Isol Reset pushbuttons

[HS-3-99Al

and[HS-3-99B].[C.1]

[n]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 67 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenance(Continued)

[9]WHEN desired to shutdown MG Set A, THEN PERFORM the following:

NOTE The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional

Overcurrent

Relay contacts.[a]IF the reactor trip breakers are CLOSED, THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99Al

and[HS-3-99B].

2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset Pushbuttons

[HS-3-99Al

and

[b]OPEN MG Set A Load (GENERATOR)

Breaker 52-1 USING[HS-85-12].

NOTE Voltage will be maintained

for a short time after opening the motor circuit breaker due to an intended time delay.[c]STOP CRD MG Set A by placing MOTOR Breaker 52A Circuit Control in the TRIP position USING[HS-85-1A].

[d]VERIFY MG Set A speed decreases.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 68 of 77 Unit Date_8.5 Placing MG Set A In Service for Maintenance(Continued)

NOTE The following step maybe NA if returned to normal by the clearance process.[10]WHEN maintenance

complete, AND Reactor Trip and Bypass breakers ready to return to normal, THEN PERFORM the following:

[a]ENSURE Reactor Trip Bypass breakers BYA and BYB are OPEN and RACKED OUT.BYPASS OPENRACKED OUT BREAKERBYA D D BYB D D[b]ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKERRTA D RTB D[c]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts.End of Section 8.5

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 69 of 77 Date----Placing MG Set B In Service for Maintenance

Unit------8.6[1]ENSURE clearance in place to isolate power to Rod Control coils on reactor head AND RECORD Hold Order Number.[2]START CRD MG Set 8 by placing[HS-85-1 B]MOTOR Breaker 528 Circuit Control in the CLOSE position.D NOTE Allow 15

for the MG set to obtain full rated speed.[3]VERIFY generator speed increasing.

[4]WHEN generator has increased to full speed, THEN[a]DEPRESS AND HOLD Gen Field Flash pushbutton.

[b]WHEN voltage is>250 volts, THEN RELEASE Gen Field Flash pushbutton.

[5]IF Line Voltage of the MG set is NOT between 255 and 270 volts (260 volts is nominal), THEN ADJUST voltage with WTV Reg to a nominal 260 volts.NOTE Voltage may vary slightly between phases.[6]CHECK voltage approximately

equal on all phases using voltmeter selector switch.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 70 of 77 Date----Placing MG Set B In Service for Maintenance

Unit------8.6[7]WHEN Maintenance

requires MG Set B Load Breaker to be closed THEN PERFORM the following:

NOTE Both MG Set Load Breakers must be RACKED IN prior to closing the running MG Set Load Breaker.[a]ENSURE MG Set A Load (GENERATOR)

Breaker 52-1[BCTF-85-12l

is RACKED IN.[b]ENSURE MG Set B Load (GENERATOR)

Breaker 52-2[BCTF-85-22l

is RACKED IN.[c]ENSURE CRDM MG Set B Directional

Overcurrent

Relay Target Coils for are RESET (Panel Pushbutton).(N/A other Unit)Relay INITIALS[1-RL Y-085-DF/3B/A]

(67 A)[1-RLY-085-DF/3B/C]

(67C)[2-RLY-085-DH/3B/Al

(67A)[2-RL Y-085-DH/3B/C]

(67C)[d]ENSURE targets for CRDM MG Set B Directional

Overcurrent

Relays are RESET (Mechanical

Linkage on relay).(N/A other Unit)Relay INITIALS[1-RLY-085-DF/3B/A]

(67A)[1-RL Y-085-DF/3B/Cl

(67C)[2-RLY-085-DH/3B/A]

(67A)[2-RL Y-085-DH/3B/Cl

(67C)

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 71 of 77 Date_Placing MG SetB In Service for Maintenance

Unit------8.6 NOTE Generator voltage will drop slightly as the electrical

load increases.

[e]CLOSE MG Set B Load (GENERATOR)

Breaker 52-2 USING[HS-85-22].

IF another trip of breaker 52-2 occurs, THEN REPEAT substeps[a],[b]and[c].IF breaker 52-2 trips the third time, THEN NOTIFY SM and System Engineering

for assistance.

[5][f]IF MG Set B Load breaker 52-2 trips due to Directional

Overcurrent

Relay operation, THEN[1]RESET Directional

Overcurrent

Relays with Relay Target Reset Button on Relay panel.[2]RESET Directional

Overcurrent

Relay Targets.[3]RECLOSE MG Set A load Breaker 52-2.[4][8]WHEN MAINTENANCE

requiresreactortrip/bypass

breakers to be closed, THEN PERFORM the following:

[a]ENSURE[1CB], Auxiliary 150-VAC Supply to Rod Drive System is CLOSED.(located in Panel L-115).[b]ENSURE lift coil disconnect

switches, for Control Rods and Shutdown Rods are in the CONNECTED position (located on M-8).

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 72 of 77 Date----Placing MG Set B In Service for Maintenance

Unit------8.6 CAUTION ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4)should never be held in STARTUP position for any extended period of time.Holding this switch in STARTUP position may cause damage to the counters.[c]MOMENTARILY

PLACE[SUS], Rod Control Startup Step Counter Reset to the STARTUP position to reset Control Rod Drive System, AND VERIFY group step counters are at zero steps.[d]ENSURE Reactor Trip Bypass breakers are in required alignment per maintenance

procedure.

BYPASS RACKED IN RACKED OUT BREAKERBYA D D BYB D D[e]ENSURE Reactor Trip breakers are in required alignment.t d per main enance proce ure.TRIP RACKED IN RACKED OUT BREAKERRTA D D RTB D D Cco,[f]ENSURE control power is ON by GREEN indicating

lights on M-4: (NA breakers not racked in)BREAKER GREEN INITIALS LIGHT RTA ON RTB ON BYA ON BYB ON[g]ENSURE Rod Control switch[HS-85-51111

is in MID position.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 73 of 77 Unit Date_8.6 Placing MG Set B In Service for Maintenance

[h]IF unit is in Mode 3,THEN ENSURE requirements

of Tech Spec 3.4.1.2 are met.[i]DEPRESS and HOLD FW Isol Reset pushbuttons

[HS-3-99Al

and[HS-3-99Bl.[C.1]

[j]IF maintenance

being performed on Unit 1, THEN CLOSE Rx Trip Breakers by placing[1-RT-1], to CLOSE position.[k]IF maintenance

being performed on Unit 2, THEN CLOSE Rx Trip Breakers by placing[2-HS-99-7], to CLOSE position.[I]VERIFY Reactor Trip Breakers/Reactor

Trip Bypass breakers CLOSED by RED indicating

lights on M-4: (NA breakers not closed)BREAKER RED LIGHT INITIALS RTA ON RTB ON BYA ON BYB ON[m]RELEASE FW Isol Reset pushbuttons

[HS-3-99A]

and[HS-3-99B].[C.1]

[n]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts.

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 74 of 77 Unit Date_8.6 Placing MG Set B In Service for Maintenance

[9]NOTE WHEN desired to shutdown MG Set B, THEN PERFORM the following:

The MG set Load Breakers may trip open when the reactor trip breakers are opened due to the vibration problem on the Directional

Overcurrent

Relay contacts.[a]IF the reactor trip breakers are CLOSED, THEN 1.DEPRESS AND HOLD Feedwater Isolation Reset Pushbuttons

[HS-3-99A]

and[HS-3-99B]

2.OPEN the reactor trip breakers.3.RELEASE Feedwater Isolation Reset Pushbuttons

[HS-3-99Al

and[HS-3-99Bl

[b]OPEN MG Set B Load (GENERATOR)

Breaker 52-2 USING[HS-85-22].

NOTE Voltage will be maintained

for a short time after opening the motor circuit breaker due to an intended time delay.[c]STOP CRD MG Set B by placing MOTOR Breaker 52B Circuit Control in the TRIP position.USING[HS-85-1B].

[d]VERIFY MG Set B speed decreases.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 75 of 77 Unit Date----8.6 Placing MG Set B In Service for Maintenance

NOTE The following stepmaybeNA if returned to normal by the clearance process.[10]WHEN maintenance

complete AND Reactor Trip and Bypass breakers ready to return to normal, THEN PERFORM the following:

[a]ENSURE Reactor Trip Bypass breakers BY A and BYB are OPEN and RACKED OUT.BYPASS OPEN (-V)RACKED OUT BREAKERBYA D D BYB D D[b]ENSURE Reactor Trip breakers are RACKED IN: TRIP RACKED IN BREAKERRTA D RTB D[c]NOTIFY IMs to perform 1 ,2-PI-IFT-099-0P4.0, Verification

of P4 Contacts.End of Section 8.6

SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 32 Page 76 of 77 9.0 RECORDS A.Completed copies of sections shall be transmitted

to the Operations

Superintendent's

Secretary.

SQN CONTROL ROD DRIVE SYSTEM 0-80-85-1 1,2 Rev 32 Page 77 of 77 SOURCE NOTES Page 1 of 1 IMPLEMENTING

STATEMENT[C.1][C.2]REQUIREMENTS

DOCUMENT NC00940183003

8Q94026311

LER327/94005

LER328/94008

REQUIREMENTS

STATEMENT Revised procedure to require feedwater isolation reset buttons to be held during closure of reactor trip breakers.Revised procedure to operate the thrust switch in a more conservative

method to minimize the possibility

of step deviations

greater than two steps during initial rod movement.

0.

JPM B.1.d Page 10f 9 Rev.0 SEQUOYAH NUCLEAR PLANT JOB PERFORM*ANCE

MEASURE B.1.d JPM FILLI'NG AND VENTING EXCESS LETDOWN PREPAREDI REVISED BY: VALIDATED BY:*APPROVED BY: (Operations

Training Manager)Date/Date/Date/CONCURRED:

    • (Operations

Representative)

Date/*Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual

step changes that do not affect the flow of the JPM.**Operations

Concurrence

required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM B.1.d Page 2 of 9 Rev.0 I NUCLEAR TRAINING REVISION/USAGE

LOG REVISION DESCRIPTION

OF V DATE PAGES PREPAREDI NUMBER REVISION AFFECTED REVISED BY: 0 New Y Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.

JPM B.1.d Page 3 of 9 Rev.0 SEQUOYAH NUCLEAR PLANT RO/SRO JOBPERFORMANCEMEASURE

Task: Filling and Venting Excess Letdown JAITA task:#0040160101 (RO)Place Excess Letdown in Service KIA Ratings: 004 Chemical And Volume Control System A4 Ability to manually operate and/or monitor in the control room (CFR 41.7/45.5 to 45.8)A4.06 Letdown isolation and flow control valves 3.6/3.1 Task Standard: 1)Excess letdown is filled and vented in accordance

with 1-S0-62-6, Excess Letdown, section 8.1 Evaluation

Method: Simulator__X_In-Plant_===================================================================================

Performer:

Performance

Rating: SAT Evaluator:

NAME UNSAT SIGNATURE Performance

Time DATE Start Time_Finish Time_==============.=====================================================================

COMMENTS

JPM B.1.d Page 4 of 9 Rev.0 SPECIAL INSTRUCTIONS

TO EVALUATOR:

1.Sequenced steps identified

by an"s" 2.Any UNSAT requires comments 3.This task is to be performed using the simulator in Ie 6.4.Ensure operator performs the following required actions for SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.9 min Local-----Tools/Equipment/Procedures

Needed: 1-S0-62-6 References:

1.1-S0-62-6 Excess Letdown Title Rev16=.============================================================================

READ TO OPERATOR Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job*performance

measure will be satisfied.

Ensure you indicate.tome when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.Plant is in Mode 3.2.Excess letdown system has been out of service for maintenance.

3.The work is complete and the system is ready to be filled and vented.2.You are an extra RO on shift INITIATING

CUES: 1.The SRO has directed you to fill and vent Excess Letdown.2.You are to notify the SRO when you have completed filling and venting Excess Letdown in accordance

with1-S0-62-6, Excess Letdown.3.Section 4, Prerequisites

Actions, has been completed.

Job Performance

Checklist STEP/ST ANDARD JPM B.1.d Page 50f9 Rev.0 SAT/UNSAT STEP 1.: Obtain the appropriate

procedure.

-SAT-UNSAT STANDARD: Operator identifies

1-S0-62-6 and goes to section 8.1"Filling and Venting Excess Letdown".Start Time--COMMENTS: STEP 2.: NOTE An AUO at panel O-L-2 will be needed to observe an increase in the-SAT RCDT level.-UNSAT Cue: When AUO is directed to O-L-2, Acknowledge

the direction STANDARD: An AUO is directed to be stationed at panel O-L-2 to observe RCDT level.COMMENTS: STEP 3.:[1]ENSURE

CCS water to Excess Letdown Heat Exchanger is-SAT OPEN.-UNSAT STANDARD: Candidate determines

l-FCV-70-143

is open by the red light lit above 1- EXCESS LETDOWN HX INLET ISOL, on O-M-278.COMMENTS: STEP 4.:[2]OPEN[1-FCV-70-85]

Excess Letdown Heat Exchanger CCS Flow Control.-SAT-UNSAT STANDARD: Candidate places 1-HS-70-85A, EXCESS LETDOWN HX OUTLET ISOL, to the OPEN position on O-M-278 and Holds until the valve is full open (red light is lit and the green light light is dark.)Criti.cal Step COMMENTS:

Job Performance

Checklist STEP/ST ANDARD JPM B.1.d Page 6 of 9 Rev.0 SAT/UNSAT STEP 5.:[3]PLACE[1-FCV-62-59]

Excess Letdown 3-way Divert Valve in DIVERT.-SAT-UNSAT STANDARD: Candidate places 1-HS-62-59, EXCESS LTDN DIVERT, to the DIVERT position on 1-M-5.Right side red light will be lit, left side red light will be dark.Critical.Step COMMENTS: STEP 6.:[4]OPEN[1-FCV-62-54]

Cold Leg Loop#3 Excess Letdown Isolation Valve.-SAT-UNSAT STANDARD: Candidate places 1-HS-62-54A, Excess Letdown Isolation, to the OPEN position on 1-M-5.Red light above handswitch

will be lit.Critical COMMENTS: Step STEP 7.:[5]OPEN[1-FCV-62-55]

Excess Letdown Containment

Isolation Valve.-SAT-UNSAT STANDARD: Candidate places 1-HS-62-55A, Excess Letdown Isolation, to the OPEN position on 1-M-5.Red light above handswitch

will be lit.Critical Step COMMENTS:

Job Performance

Checklist STEP/ST ANDARD JPM B.1.d Page 7 of 9 Rev.0 SAT/UNSAT STEP 8.:[6]OPEN[1-FCV-62-S6]

Excess Letdown Flow Control Valve.-SAT Note: The procedure contains this note prior to the step-UNSAT"NOTE At the completion

of step[6]a timed duration will be initiated." Cue: After the FCV is opened, state that 5 minutes has elapsed.Critical Step STANDARD: Candidates

rotates handswitch

1-HIC-62-56, Excess L TDN Flow Control Valve, to the counter-clockwise

to greater than the'0" position on 1-M-5.Evaluator Note: Temperature

and pressure rise will be indicated on 1-TI-62-58 and 1-PI-62-57 respectively

Cue: If Excess Letdown Hx Temp alarm comes in, state that the temperature

is high but has stabilized.

COMMENTS: STEP 9.:[7]OBSERVE level increase in RCDT for 5 minutes-SAT-UNSAT Cue: When AUO contacted, state"The RCDT level has been continuously

increasing

for the last 5 minutes-" STANDARD: AUO is contacted to monitor RCDT level.(RDCT level can also be monitored on the ICS)COMMENTS: STEP 10.: 8]WHEN 5 minutes haselapsed,THEN

CLOSE[1-FCV-62-S6]

Excess-SAT Letdown Flow Control Valve.-UNSAT STANDARD: Candidates

rotates handswitch

1-HIC-62-56, Excess L TDN Flow Control Valve, on 1-M-5, clockwise to the'0" position.Critical Step COMMENTS:

Job Performance

Checklist STEP/STANDARD

STEP 11.:[9]CLOSE the following valves: JPM B.1.d Page 8 of 9 Rev.0 SAT/UNSAT SAT VALVE UlENTIFICA

TIO:N lNITIAlS UNSAT l-FCV-62-55

Ex.;cl:.s.s

Letdklvm Conlainrnent

Isolaticn l-FCV-02...Et4.C,old Leg Loc:p#3

Letdown

l-FCV-7"G'-B5

Ex:C*ss LetdCfim Heat Exchang?ef" CCS FCV Critical Step Cue: If IV is requested, state"An individual

will be assigned to performed the IV" STANDARD: Candidate closes the the listed valves by placing the respective

handswitches

(1-HS-62-55

&1-HS-62-54

on 1-M-5, and 1-HS-70-85

onM-27B)to the CLOSE position.Red light will go dark and green light will be lit.COMMENTS: STEP 12.:[10]PLACE[1-FCV-62-59]

Excess Letdown 3-way Divert Valve in NORMAL.STANDARD: Candidate places 1-HS-62-59, EXCESS L TDN DIVERT, on 1-M-5 to the NORMAL position.Right side red light will be dark, left side red light will be lit.COMMENTS: STEP 13.: Notifcation

of completion

of 1-S0-62-7 is made to the SRO.STANDARD: SRO is notified that Excess Letdown is filled and vented.COMMENTS: End of JPM SAT UNSAT Critical Step SAT UNSAT Stop Time__

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION

OF TASK)DIRECTION TO TRAINEE:'I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating

cues and reports on other actions when directed by you.Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.IN.ITIAL CONDITIONS:

1.Plant is in Mode2.Excess letdown system has been out of service for maintenance.

3.The work is complete and the system is ready to be filled and vented.2.You are an extra RO on shift.INITIATING

CUES: 1.The SRO has directed you to fill and vent Excess Letdown.2.You are to notify the SROwhen YO'u have completed filling and venting Excess Letdown in accordance

with 1-S0-62-6, Excess Letdown.3.Section 4, Prerequisites

Actions, has been completed.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION

1-50-62-6" EXCESS LETDOWN Revision 16 QUALITY RELATED MS LEENERTS OPERATIONS

RESPONSIBLE

ORGANIZATION:

w.T.LEARY APPROVED BY:

EFFECTIVE DATE: 06/05/07 LEVEL OF USE: CONTINUOUS

USE REVISION DESCRIPTION:

Revised Attachment

2 to change position of 1-70-702C from CLOSED&CAPPED to LOCKED CLOSED&CAPPED and changed verification

from IV to CV (NB070420).

THIS PROCEDURE COULD AFFECT REACTIVITY

SQN EXCESS LETDOWN 1-S0-62-6Rev:16 1 Page 2 of 14 TABLE OF CONTENTS Page 1 of 1 Section Title Page 1.0 INTRODUCTION

3 1.1 Purpose*.................................................................................................................

3 1.2 Scope 3 2.0 REFERENCES

3 2.1 Performance*

References.....

3 2.2 Developmental

References....................................

3 3.0 PRECAUTIONS

AND LIMITATIONS

4 4.0 PREREQUISITE

ACTIONS 5 5.0 STARTUP/STANDBY

READINESS 6 6.0 N*ORMAL OPERATION 9 7.0 SHUTDOWN 10 8.0 INFREQUENT

OPERATION 12 8.1 Filling and Venting Excess Letdown 12 9.0 RECORDS 14 ATTACHMENTS

ATTACHMENT

1: POWER CHECKLIST 1-62-6.01 ATIACHMENT

2: VALVE CHECKLIST 1-62-6.02

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 30f 14 1.0 INTRODUCTION

1.1 Purpose To provide instructions

for the operation of excess letdown.1.2 Scope A.Placing excess letdown in service.B.Ta-king excess letdown out of service.2.0 REFERENCES

2.1 Performance

References

None.2.2 Developmental

References

A.801-62.1, Chemical and Volume Control System B.1-80-62-1, Chemical and Volume Control System C.TVA Drawings 1.47W809-1 2.47W859-2 D.SQN-VTM-1201-0010

Grinnell Valve vendor manual

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 4 of 14 3.0 PRECAUTIONS

AND LIMITATIONS

A.Failureto observe all posted radiation control requirements

may lead to unnecessary

radiation absorbed doses.B.When placing Excess Letdown in service to replace normal letdown, the charging flow temperature

may cool enough to lower the ReS average temperature

and may cause a change in reactivity.

C.The fluid outlet temperature

of the excess letdown heat exchanger-should

not exceed 200°F.The maximum allowable temperature

is 250°F.D.While placing the excess letdown heat exchanger in service the Rep seal leakoff flow may fluctuate, therefore periodic monitoring

should be maintained.

E.When Excess Letdown is placed in service an approximate

increase of 100 CPM maybe observed on 1-RM-90-106A.

This elevated radiation monitor reading should start to trend back to normal after approximately

one hour.F.Operation of Excess Letdown with 1-TI-62-58 (Excess Letdn Temp)greater than 200°F will require that Systems Engineering

be notified so that an evaluation

of Grinnell valve maintenance

can be conducted.

SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 5 of 14 Date-------4.0 PREREQUISITE

ACTIONS NOTE Throughout

this Instruction, where an IFITHEN statement exists, the step should be N/A if condition does not exist.[1]ENSURE Instruction

to be used is a copy of effective version.[2]VERIFY CVCS system is in service in accordance

with Valve Checklists

1-62-1.03 and 1-62-1.04.

[3]ENSURE Attachment

1, Power Checklist 1-62-6.01 has been completed.

[4]ENSURE Attachment

2, Valve Checklist 1-62-6.02 has been completed.

[5]ENSURE Precautions

and Limitations, Section 3.0 have been reviewed.[6]ENSURE each performer documents their name and initials:/""\Print Name Initials I

b/'t:>oK,5

)-[7]INDICATE below which performance

section of this instruction

will be used and the reason for this performance:

o 5.0 STARTUP/STANDBY

READ.INESS

REASON: INFREQUENT

OPERATION c7 I o 7.0 SHUTDOWN W 8.0

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 6of14 Date----5.0 STARTUP/STANDBY

READINESS NOTE 1 NOTE 2 When excess letdown is placed in service the containment

radiation monitors may show some changes in particulate

reading.Coordinate

the following steps with AUO stationed at O-L-2 to monitor RCDT for pump operation as required during the 50 gallon flush.[1]ENSURE[1-FCV-62-931

is in MANUAL and[a]OPERATE[1-FCV-62-931

USING[1-HIC-62-93A]

as required to regulate charging flow to keep pressurizer

level,on program.[b]OPERATE[1-FCV-62-89]

USING[1-HIC-62-89A]

as required to maintain Rep seal flows in limits.[2]NOTIFY RADCON that Excess Letdown is being placed in service.[3]ENSURE[1-FCV-70-1431

CCS water to the excess letdown heat exchanger is OPEN.[4]ENSURE[1-FCV-70-851

Excess Letdown Heat Exchanger CCS flow control valve is OPEN.NOTE Step[5]will prevent subjecting

the cves piping downstream

of the Excess Letdown HX to a temperature

above the design value.[5]ENSURE[1-FI-70-841

is indicating

greater than 230 gpm.[6]PLACE[1.-FCV-62-591

Excess Letdown 3-way Divert Valve in DIVERT.

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 7 of 14 Date----5.0 STARTUP/STANDBYREADINESS(Continued)

CAUTION NOTE FCV 62-63 has replaced RCP seal leak-off isolation valves as the primary means for isolating seal flow.The normal letdown path for excess letdown will not be available if FCV-62-63 is CLOSED.Back flow through the RCP seals will occur should the RCP seal leakoff isolation valves fail to their OPEN position on loss of air or electrical

p.ower.[7]IF less than 100 psig in RCS and[1-FCV-62-63l

is CL*OSED and excess letdown will be aligned for NORMAL operation, THEN[a]ENSURE the following are CLOSED: VALVEID FUNCTION INITIALS 1-FCV-62-53

RCP's Seal Bypass 1-FCV-62-9

No.1 Seal Return 1-FCV-62-22

NO.2 Seal Return 1-FCV-62-35

NO.3 Seal Return 1-FCV-62-48

NO.4 Seal Return[b]ENSURE[1-FCV-62-63]is

OPEN.[8]OPEN[1-FCV-62-54]

Cold Leg Loop#3 Excess Letdown isolation valve.[9]OPEN

Excess Letdown containment

isolation valve.

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 8 of 14 Date----5.0 STARTUP/STANDBY

READINESS(Continued)

NOTE ICS point 1 L2400A or the AUO stationed at 0-L-2 can be used to monitor RCDT for level increase during the 50 gallon flush.Reference the RCDT Level vs Volume table in TI-28.[10]OPEN[1-FCV-62-561

slowly to flush piping to RCDT.[11]WHEN approximately

50 gallons have flushed, THEN CLOSE[1-FCV-62-56], Excess Letdown Flow Control Valve.1st IV[12]PLACE[1-FCV-62-59]

Excess Letdown 3-way Divert Valve in NORMAL.1st IV NOTE 1 NOTE 2 Normally the temperature

read on 1-TI-62-58

should be less than 200°F.If operation requires temperatures

greater than 200°F, the pressure at 1-PI-62-64 (local indicator EI.690 Pnl L-46)should be less than 100 psig to protect the Grinnell valves.Operation above 200°F will require that Systems Engineering

be notified to allow an evaluation

of the need for valve maintenance.

[13]OPEN[1-FCV-62-561

slowly to increase excess letdown flow to desired amount, not to exceed 240°F heat e*xchanger

outlet temperature, as indicated on 1-TI-62-58.

NOTE Placing Excess Letdown in service causes increased activity in various areas of the Auxiliary Building.[14]NOTIFY RADCON thatExcess

Letdown has been placed in service.END OF TEXT

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 9 of 14 6.0 NORMAL OPERATION None.

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 10 of 14 Date 7.0 SHUTDOWN[1]IF letdown is to be placed in service, THEN RETURN to service per 1-S0-62-1.

[2]C*LOSE[1-FCV-62-56]

Excess Letd.own Heat Exchanger outlet valve.1 st IV[3]VERIFY[1-FCV-62-59]Excess Letdown 3-way valve in NORMAL.1 st IV[4]CLOSE[1-FCV-62-55]

Excess Letdown containment

isolation valve.1 st IV[5]CLOSE[1-FCV-62-54]

Cold Leg Loop#3 Excess Letdown valve.1st IV[6]IF charging is in service, THEN ADJUST seal injection flow to 6-11gpm using[1-FCV-62-89].

[7]IF auto operation is desired and system conditions

will allow it, THEN PLACE[1-FCV-62-93]

in AUTO.[8]NOTIFY RADCON that Excess Letdown is REMOVED from SERVICE.

SQN EXCES5LETDOWN

1-50-62-6Rev:16 1 Page 11 of 14 Date_7.0 SHUTDOWN[9]ENSURE[1-FCV-70-851

Excess Letdown HX CCS Flow Control Valve is CLOSED.[10]ENSURE[1-HS-70-85Al

is in the A-AUTO position.[11]IF operation at greater than 200 of has occurred, THEN CONTACT Systems Engineering

to evaluate Grinnell valve maintenance

requirements.

E*ND OF TEXT 1st 1 st IV IV

SQN EXCESS LETDOWN 1-50-62-6 Rev: 16 1 Page 12 of 14 Date----8.0" INFREQUENT

OPERATION 8.1 Filling and Venting Excess Letdown NOTE An AUG at panel O-L-2 will be needed to observe an increase in the RCDT level.[1]ENSURE[1-FCV-70-1431

CCS water to Excess Letdown Heat Exchanger is OPEN.[2]OPEN[1-FCV-70-85l

Excess Letdown Heat Exchanger CCS Flow Control.[3]PLACE[1-F"CV-62-59]

Excess Letdown 3-way Divert Valve in DIVERT.[4]OPEN

Cold LegLoop#3 Excess Letdown Isolation Valve.[5]OPEN[1-FCV-62-55]

Excess Letdown Containment

Isolation Valve.NOTE At the completion

of step[6]a timed duration will be initiated.

[6]OPEN[1-FCV-62-56]

Excess Letdown Flow Control Valve.[7]OBSERVE level increase in RCDT for 5 minutes.[8]WHEN 5 minutes has elapsed, THEN CLOSE[1-FCV-62-561

Excess Letdown Flow Control Valve.1 st IV

SQN EXCESS LETDOWN 1-S0-62-6Rev:16 1 Page 13 of 14 Date-------8.1 Filling and Venting Excess Letdown (Continued)

[9]CLOSE the following valves: VALVE IDENTIFICATION

INITIALS 1-FCV-62-55

Excess Letdown Containment

Isolation-1-st-IV 1

Cold Leg Loop#3 Excess Letdown Isolation-1-st-IV 1-FCV-70-85

Excess Letdown Heat'Exchanger

CCS FCV-1-st-IV[10]PLACE[1-FCV-62-59]Excess Letdown 3-way Divert Valve in NORMAL.END OF TEXT 1 st IV

SQN EXCESS LETDOWN 1-S0-62-6 Rev: 16 1 Page 14 of 14 9.0 RECORDS Completed copies of all Sections shall be transmitted

to the Operations

Superintendents

Secretary.

u.S c....l S;a CD

PREPAREDI REVISED BY: JPM#75AP Page 1 of 10 Rev.8 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE

MEASURE B.1.e JPM#75-AP SteamGeneratorTube

Rupture (With MSIV Failure to Close)Date/VALIDATED BY:*APPROVED BY: Date/Date!(Operations

Training Manager)CONCURRED:

    • Date/(Operations

Representative)

  • Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual

step changes that do not affect the flow of the JPM.**Operations

Concurrence

required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM#75AP Page 2 of 10 Rev.8 r NUCLEAR TRAINING REVISION/USAGE

LOG REVISION DESCRIPTION

OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 3 Transfer from WP.Minor enhancements.

N 10/15/94 All HJ Birch 4 Incorporate

Rev B changes.Changed to Y 9/16/95 All HJ Birch S/G#1 to force swap of TDAFW steam supply.pen/ink Added closed, to verify Atm Relief vlvs in N 12/7/95 5,6 HJ Birch auto.Also enhance standard for MSIV bypasses nota JPM critical task.E-O Rev chg only.N 2/6/97 4 HJ Birch pen/ink revision had no impact N 8/11/98 All JP Kearney pen/ink E-O Rev chg only.N 9/23/99 4 SR Taylor pen/ink E-O Rev 22 chg only.E-3 Rev 12 minor N 09/05/01 ALL WR Ramsey changes 5 Incorporated

pen/ink changes N 8/22/02 AllJP Kearney 6 Updated to current revision and IC.N 8/10/04 All MG Croteau 7 Updated references

and reordered steps N 10/28/200 ALL JJ Tricoglou to conform to the latest revision to E-3.5 Deleted Critical Step 9 as this*step was deleted from the procedure 8 Update to E-3 rev 17, added candidate N All handout sheet, modified instructions

and steps to reflect instruction

revision and provide clarity.v-Specify if the JPM change will require another validation (Yor N).See cover sheet for criteria.

JPM#75AP Page 3 of 10 Rev.8 SEQUOY AH NUCLEAR PLANT RO/SRO JOB PERFORMANCE

MEASURE Task: Steam Generator Tube Rupture (With MSIV Failure to Close)JAlTA task#: 0000380501 (RO)KIA Ratings: 038EA1.32 (4.6-4.7)Task Standard: Steam Generator#1 isolated per E-3.Evaluation

Method: Simulator__X__In-Plant_====================================================================================

Performer:*

Performance

Rating: SAT Evaluator:

NAME UNSAT SIGNATURE Performance

Time DATE Start Time__-,--Finish Time_====================================================================================

COMMENTS

JPM#75AP Page 4 of 10 Rev.8 SPECIAL INSTRUCTIONS

TO EVALUATOR:

1.Sequenced steps identified

by an"s" 2.AnyUNSAT requires comments 3.Initialize

simulator in IC#175.4.If snapshot unavailable, then Initialize

simulator in IC#16 and Insert the following:

a.Activate malfunction

IMF TH05A f:8.5 to initiate S/G tube rupture in S/G#1.b.Activate malfunction

IMF MS14A f:100, to fail open S/G Loop 1 MSIV.c.Complete the actions of E-O thru step 12, which will transition

the crews to E-3 d.Complete any required actions in ES-0.5.Including closing the TD AFW LCVs, but do not put handswitches

in pull-to-Iock.

e.Complete the first three ste.ps in E-3.f.Actuate a MANUAL reactor trip and safety injection, take all actions up through Step 3 of E-3.5.Freeze the simulator until the operator is ready to begin the JPM.6.Ensure operator performs the following required actions for SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.12 mins Local_Tools/Equipment/Procedures

Needed: E-3 References:

Rev No.A.E-O Reactor Trip or Safety Injection 29 B.E8-0.5 Equipment Verifications

0 C.E-3 Steam Generator Tube Rupture 17=======================================================

Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

Unit 1 has experienced

a SGTR.A manual safety injection was initiated and E-O implemented.

E-O and E.S-0.5 have been completed and a transition

to E-3 has been made.Steps 1 through 3 of E-3 have been completed and S/G#1 has been identified

as the ruptured S/G.INITIATING

CUES: You are the eRO and are directed to continue with the actions/responses

of 6-3, beginning at Step 4.Inform the SRO when you are ready to determine the Target Core Exit Thermocouple

temperature.

Job Performance

Checklist:

STEP/STANDARD

JPM#75AP Page 5 of 10 SAT/UNSAT STEP 1.: Obtain appropriate

copy of procedure.

-SAT STANDARD: Operator obtains a copy of E-3 andcontinuesat

step 4 as directed.-UNSAT COMMENTS: Start Time--STEP 2.:[4.a]ADJUST Ruptured S/Gs atmospheric

relief controller

setpoint to-SAT 87%in AUTO.(1040 psig)-UNSAT STANDARD: Operator adj.usts PIC-1-6A to 87%and ensures the controller

is in auto.Critical Step COMMENTS: SToEP 3.:[4.b]CHECK Ruptured S/G atmospheric

relief handswitch

in P-AUTO-SAT and CLOSED.-UNSAT STANDARD: Operator checks S/G#1 atmospheric

relief HS, FCV-1-6, on 1-M-4in P-AUTO and checks green light LIT abovehandswitch.

COMMENTS: STEP 4:[4.c]CLOSE TD AFW pump steam supply from Ruptured S/G FCV-1--SAT 15 (S/G#1)or FCV-1-16 (SIG#4).-UNSAT STANDARD: Operator closes FCV-1-15 and verifies closed by GREEN light LIT ON 1-M-4[Critical part of step].May verify that FCV-1-16, S/G#4, auto opens or may open valve manually, approx 1 minute later, with red light Critical Step LIT, not critical).

COMMENTS: STEP 4.:[4.d]VERIFY RupturedS/G

blowdown isolation valves Closed.-SAT STANDARD: Operator verifies FCV-1-7 and

CLOSED as indicated by-UNSAT green indication

lights above handswitch

1-HS-1-7/181

on 1-M-4.COMMENTS:

Job Performance

Checklist:

STEP/ST ANDARD JPM#75AP Page 6 of 10 SAT/UNSAT STEP 5.:[4.e]CLOSE Ruptured S/G MSIV and MSIV Bypass Valve.-SAT Note: SIG#1 MSIV will NOT close and the operator MUST go to theRNO-UNSAT column at this time.STANDARD: Attempts to close MSIV FSV-1-4.Recognizes

the MSIV failed to close, by the red light LIT, and goes to RNO to isolate the S/G.COMMENTS: STEP 6.:[4.e.1]CLOSE IntactS/G MSIVs and MSIV bypass valves.-SAT Cue: When operator dispatches

an AUO to close SG#1 MSIV with

-UNSAT acknowledge

the direction.

Critical Step STANDARD: Operator closes intact S/G MSIVs and verifies their bypasses closed as indicated by blue and green lights LIT on HS-1-11 ,-22,&-29 MSIVs and Green lights LIT on HS-1-147,-148,-149,-150

bypasses.[Ensuring the bypasses closed isnotaJPM critical task since valves are already closed.]COMMENTS: STEP 7.:[4.e.2]Dispatch operator to perform EA-1-1, Closing MSIVs Locally, for-SAT any MSIV or MSIV bypass valve which fails to close.-UNSAT Cue: If operator dispatches

an AUO to close SG#1 MS/V with EA-1-1 acknowledge

the direction.

STANDAR.D:

Operator dispatches

an AUO to close MSIV FSV-1-4 using EA-1-1.COMMENTS: STEP 8.-:[4.e.3]Isolate steam header-SAT*PLACE Condenser steam dumps in OFF*ENSURE steam dump valves CLOSED.-UNSAT STANDARD: Operator verifies Condenser Steam dumps are closed as indicated by Critical Step green position indicating

lights LIT on1-XX-55-4A

and places the handswitch(s)

1-HS-1-1 03A and/or 1-HS-1-1 03B in the OFF position on 1-M-4.COMMENTS:

Job Performance

Checklist:

STEP/ST ANDARD JPM#75AP Page 7 of 10 SAT/UNSAT STEP 9.: CLOSE FCV-47-180, HP Steam Seal Supply Isolation-SAT STANDARD: Operator Verifies Steam seals closed as indicated by green light LIT on-UNSAT 1-HS-47-180

OR AUO dispatched

to close local isolation valve on 1-M-2.Critical Step COMMENTS: STEP 10.: ENSURE FCV-47-181, HP Steam Seal Supply Bypass CLOSED.-SAT-UNSAT STAN.DARD:

Operator Verifies HP steam to MFW pump turbine closed as indicated by green light LIT on 1-HS-47-181

on 1-M-2.COMMENTS: STEP 11..: CLOSE MSR HP Steam supply isolation valves.-SAT-UNSAT STANDARD: Operator closes HP steam to MSRs as indicated by green position indicating

lights LIT on 1-XX-1-145, MSR HP Steam Supply Status, Critical Step on 1-M-2 for each of the valves.Two valves on each of the six MSR's have to be closed from the handswitches

on 1-M-2.COMMENTS: STEP 12.: DISPATCH operator to locally isolate steam header USING EA--SAT 1-4, Local Isolation of the Steam header in the Turb Bldg.-UNSAT C*ue: When operator dispatches

an AUO to isolate steam header USING EA-1-4, acknowledge

the direction and provide feedback that the Critical Step traps have been isolated per EA-1-4.STANDARD: Operator directs AUO to isolate the steam header traps per*EA-1-4, Local Isolation of the Steam Header in Turb.Building.COMMENTS: STEP 13.:[4.e.4]USE intact S/Gs atmospheric

relief for steam dumps.-SAT STANDARD: Operator addresses that the atmospheric

reliefs will now have to use for-UNSAT RCS temp control.COMMENTS:

Job Performance

Checklist:

STEP/ST ANDARD JPM#75AP Page 8 of 10 SAT/UNSAT STEP 14.:[5]MONITOR Ruptured S/G level:-SAT a.CHECK narrow range level greater than 10%[25%ADV]b.WHEN ruptured S/G level is greater than 10%[25%ADV]THEN-UNSAT STOP feed flow to Ruptured S/G.1)STOP feed flow to ruptured S/G 2)ENSURE Turbine Driven AFW LeV for ruptured S/G in CLOSE PULL TO LOCK.Critical Step Cue: IF level is<10%state level is now 15%.STANDARD: Operator continues AFW flow to SG#1 until the level is?: 10%on LIS-3-42, 39, 38.THEN the*AFW flow is isolated to the SG#1 by closing the MD AFW and TD AFW level control valves.MD AFW valves closed by depressing

the push button on 1-HS-3-164A, then rotating the switch counterclockwise

to the MANUAL or MANUAL BYPASS position and placing switch to RAMP CLOSED TD AFW valve closed by momentarily

placing 1-HS-3-174

to the CLOSE position and pulling out to PULL TO LOCK.(not critical)Note: When valves are closed the green lights on

for SG#1 will be LIT.COMMENTS: STEP 15.:[6]VERIFY Rupture S/G ISOLATED from Intact S/G(s):-SAT a.CHECK either of the following conditions

SATISFIED:

  • Rupture S/G MSIVs and MSIV bypass valves CLOSED-UNSAT OR*MSIVs and MSIV bypass valves CLOS*ED on Intact S/Gs to be used forcooldown.

STANDARD: Operator determines

the intact S/G MSIVs are by the green lights LIT on handswitches

1-HS-1-11 A, 1-HS-1-22A, and 1-HS-1-29A.

Determines

intact S/G MSIV bypasses are closed by green lights LIT on 1-HS-1-148, 1-HS-1-149,1-HS-1-150

COMMENTS: STEP 16.: b.Check S/G#1 or#4 S/G ruptured.-SAT STANDARD: Operator determines

S/G#1 is ruptured and continues to thenextsub--UNSAT step (6.c.).COMMENTS:

Job Performance

Checklist:

STEP/STANDARD

JPM#75AP Page 9 of 10 SAT/UNSAT STEP 17.: c.Check TDAFW pump steam supply from rupturedS/G

-SAT ISOLATED:*FCV-1-15 (S/G#1)or FCV-1-16 (SIG#4)CLOSED.-UNSAT STANDARD: Operator verifies FCV-1-15 closed by GREEN light LIT on handswitch.

1-HS-1-15A on1 (Closed earlier in the J PM)COMMENTS: STEP 18.:[7]CHECK Ruptured S/G pressure greater than 550 psig (Unit 1)-SAT or 425 psig (Unit 2)-UNSAT STANDARD: Operator determines

the ruptured S/G (S/G#1)is greater than 500 psig as indicated on 1-PI-11-2A, 1-PI-11-2B, and 1-PI-11-5 COMMENTS: STEP.19.: Notify SRO that the#1S/G is isolated.-SAT STANDARD: Operator*informs

SRO that he/she is ready to determine the Target Core-UNSAT Exit Thermocouple

temperature.

Stop Time__COMMENTS: END OF JPM

Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be*performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be sati*sfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the han*dout sheet I provided you.IN,ITIAl CONDITIONS:

Unit 1 has experienced

a SGTR.A manual safety injection was initiated and E-O implemented.

E-O and ES-O.5 have been completed and a transition

to E-3 has been

Steps 1 through 3 of E-3 have been completed and S/G#1 has been identified

as the ruptured S/G.INITIATING

C*.UES: You are the eRO and are directed to continue with the actions/responses

of E-3, beginning at Step 4.Inform theSROwhen

you are ready to determine the Target Core Exit Thermocouple

temperature.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY PROCEDURE E-3 STEAM GENERATOR TUBE RUPTURE Revision 17 QUALITY RELATED D.A.PORTER PREPARED/PROOFREAD

BY:_.........................

RESPONS1BLE

ORGANIZATION:

OPERATIONS

w.T.LEARY EFFECTIVE DATE: 10/20107 REVISION DESCRIPTION:

Updated title of EA-201-3

Clarified guidance on initiating

cooldown with S/G atmospheric

relief valves in Substep 8.c.RNO (07001129).

Reworded Substep 4.e RNO for PER 127171 (07001167,07001333,07001569).

This procedure contains a Foldout Page and a Handout Page (2 copies).

SQN STEAM GENERA TOR TUBE RUPTURE Rev.17 FOLDOUT PAGE 51 REINITIATION

CRITERIA IF 81 has been terminated

AND either of the following conditions

occurs:*ReS subcooling

based on core exit TICs less than 40 of, OR*Pressurizer

level CANNOT be maintained

greater than 10%[20%ADV], THEN a.ESTABLISH ECCS flow by performing

one or both of the following:

  • ESTABLISH CePIT flow as necessary USING Appendix C*START CCPs or 51 pumps manually as necessary.

b.GO TO ECA-3.1, SGTR and LOCA-SubcooJed Recovery.EVENT DIAGNOSTICS

  • IF both trains of shutdown boards deenergized, THEN GO TO ECA-D.O, Loss of All AC PoweL*IF any S/G pressure dropping in an uncontrolled

manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isoiation.

  • IF any Intact S/G has level rising in an uncontrolled

manner OR has abnormal radiation, THEN STOP any deliberate

ReS cooldown or depressurization

and GO TO E-3 Step 1.TANK SWITCHOVER

SETPOINTS*IF CST level less than 5%, THEN ALIGN AFW suction to ERCW.*IF RWST level less than 27%, THEN GO TO ES-1.3, Transfer to RHR Containment

Sump.Page 1a of 41

SQN STEAM GENERA TOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 1 of3 STEP I ACTION FOP FOP FOP FOP FOP 1.1.b RNO 2.3.3.a RNO 4.b.RNO 5.a RNO S.b 8.b.8.c.6)IF 51 has been terminated

AND either of the following conditions

occurs:*ReS subcooling

based on core exit TICs less than 4CPF OR*PZr level CANNOT be maintained

greater than 10°.!c>[20%ADV}, THEN ESTABLISH ECCS flow by performing

one or both of the following:

  • ESTABLISH CePIT flow as necessary USING Appendix C*START CCPs or 81 pumps manually as necessary.

GO TO ECA-3.1.IF any S/G pressure dropping in an uncontrolled

manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation.

IF any Intact S/G has level rising in an uncontrolled

manner OR has abnormal radiation, THEN STOP any deliberate

ReS cooldown or depressurization

and GO TO E-3 Step 1.IF CST level less than 5%, THEN ALIGN AFW suction to ERCW.IF RWST leve'less than 270/0, THEN GO TO ES-1.3, Transfer to RHR Containment

Sump.MONITOR at least one Rep RUNNING.(If all Reps stopped)WHEN step 32 completed OR E-3 exited, THEN RESUME monitoring

ruptured loop T-cold.MONITOR Rep trip criteria:*At least one CCP or 81 pump RUNNING AND ReS pressure less than 1250 psig*MONITOR indications

of Ruptured 8/G(s).WHEN ruptured 8/G(5)identified, THEN PERFORM Steps 4 through 8.WHEN Ruptured S/G(s)pressure less than 1040 psig, THEN ENSURE S/G atmospheric

relief closed.MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10%[250/0 ADV].WHEN Ruptured S/G level greater than 10%[250/0 ADV], THEN STOP feed flow to ruptured S/G.WHEN ReS pressure less than 1960 psig, THEN BLOCK low steamline pressure 51.WHEN T-avg less than 540°F, THEN BYPASS steam dump interlock.

Page 1b of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 2 of3 STEP B.d ACTION WHEN core exit TICs less than target temperature, THEN 1)STOP ReS cooldown.2)MAINTAIN core exit TICs less than target

9.a.(if Intact S/G level Jess than 10%[25%ADV])RNO MAINTAIN total feed flow greater than 440 gpm and 16.c UNTIL level greater than 100/0[250/0 ADV]in at least one S/G..9.b MAINTAIN Intact S/G narrow range levels between 20%[250/0 ADV]and 50%.10.MONITOR pressurizer

PORVs and block valves: 12.MONITOR AC busses energized from start busses.15.d.MONITOR ReS pressure greater than 300 psig..16.d.MAINTAIN core exit TICs less than target temperature.

17.(if ruptured S/G pressure dropping)RNO MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):*MAINTAIN ReS cooldown rate less than 10CfF/hr.19.d.CONTINUE ReS depressurization

UNTIL any of following conditions

satisfied:

and*Both of the following:

20.b.1)ReS press less than ruptured S/G pressureAND

2)Pressurizer

Jevel greater than 10%[200/0 ADV]OR*Pressurizer

level greater than 65%OR*ReS subcooling

based on core exit TICs less than 4CfF.21.RNO (if ReS pressure dropping)MONITOR for indication

of leakage from pressurizer

PORV.26.CONTROL charging flow to maintain pressurizer

level..27.MONITOR ECCS flow NOT required: a.ReS sUbcooling

based on core exit TICs greater than 40 of b.Pressurizer

Jevel greater than 10%[20 0 h ADV].29.MONITOR if letdown can be established.(pzr level greater than 20 0 h[35%ADV])31.8 WHEN ReS pressure is less than 700 psig, RNO THEN ISOLATE CLAs.Page1cof41

SQN STEAM GENERATOR TUBE RUPTURE E..3 Rev.17 HANDOUT Page 3 of3 STEP ACTION 32.CONTROL ReS pressure and charging flow to minimize ReS-to-secondary

leakage: RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL RISING LEVEL DROPPING GREATER THAN 84%[80%ADV]AND STABLE PZRLEVEL*RAISE charging*RAISE charging*RAISE charging Less than 20°./c>fiow.flow.flow.[35%ADV]*DEPRESSURIZE

  • MAINTAIN ReS RCSUSING and Ruptured S/G(s)Substep 32.b.pressures equal.PZRLEVEL*DEPRESSURIZE
  • TURN ON*MAINTAIN ReS Between RCSUSING pressurizer

heaters.and Ruptured S/G(s)200/0[35°k>ADV]Substep 32.b.pressures equal.and 50%PZRlEVEL*REDUCE charging*TURN ON*MAINTAIN ReS Between flow.pressurizer

heaters.and Ruptured S/G(s)50%and 65%*DEPRESSURIZE

pressures equaL RCSUSING SUbstep 32.b.Greater than 650/0*REDUCE charging*TURN ON*MAINTAIN ReS flow.pressurizer

heaters.and Ruptured S/G(s)pressures equal.32.c.MONITOR ReS pressure less than 1040 psig.34.MONITOR if containment

spray should be stopped.(pressure less than 2rO psig)35.MONITOR if containment

vacuum control should be returned to normal: (less than 1.0 psig).38.MAINTAIN pressurizer

at saturation

temperature

for ruptured S/G pressure USING pressurizer

heaters.41.MONITOR Rep status.(Rep#2 running)41.a.4)MONITOR natura'circulation

Of NO Rep can be started).RNO 42.MONITOR jf source range channels should be reinstated.(IRM flux less than 10-4 0/0)42.f.WHEN shutdown monitor ALARM LEOs darkAND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.[M13]Page 1d of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 1 of3 STEP]FOP FOP FOP FOP FOP 1.1.b RNO 2.3.3.a RNO 4.b.RNO 5.a RNO 5.b 8.b.ACTION IF 81 has been terminated

AND either of the foJJowing conditions

occurs:*ReS subcooling

based on core exit TICs less than 40'F OR*pzr level CANNOT be maintained

greater than 10%[20%ADV], THEN ESTABLISH ECCS flow by performing

one or both of the following:

  • ESTABLISH CePIT flow as necessary USING Appendix C*START CCPs or SI pumps manually as necessary.

GO TO ECA-3.1.IF any S/G pressure dropping in an uncontrolled

manner or less than 140 psig AND S/G NOT isolated AND S/G NOT needed for ReS cooldown, THEN GO TO E-2, Faulted Steam Generator Isolation.

IF any Intact S/G has level rising in an uncontrolled

manner OR has abnormal radiation, THEN STOP any deliberate

Res cooldown or depressurization

and GO TO E...3 Step 1.IF CST level less than 50/0, THEN ALIGN AFW suction to ERCW.IF RWST level Jess than 27°ftJ, THEN GO TO ES-1.3, Transfer to RHR Containment

Sump.MONITOR at least one Rep RUNNING.(If all Reps stopped)WHEN step 32 completed OR E..3 exited, THEN RESUME monitoring

ruptured roop T-cold.MONITOR Rep trip criteria:*At least one CCP or 81 pump RUNNING AND ReS pressure less than 1250 psig.MONITOR indications

of Ruptured S/G(s).WHEN ruptured S/G(s)identified, THEN PERFORM Steps 4 through 8.WHEN Ruptured S/G(s)pressure less than 1040 psig, THEN ENSURE S/G atmospheric

relief closed.MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10°h,[25%ADV].WHEN Ruptured S/G level greater than 100/0[250/0 ADV], THEN STOP feed flow to ruptured S/G.WHEN ReS pressure less than 1960 psig, THEN BLOCK low steamline pressure 51.B.c.6)WHEN T-avg less than 540°F, THEN BYPASS steam dump interlock.

Page 1e of 41

SQN STEAM GENERA TOR TUBE RUPTURE Rev.17 HANDOUT Page 2 of3 STEP B.d ACTION WHEN core exit TICs less than target temperature, THEN 1)STOP ReS cooldown.2)MAINTAIN core exit TICs less than target temperature.

9.a.(if Intact S/G Jevelless than 100/0[25%ADV])RNO MAINTAIN total feed flow greater than 440 gpm and 16.c UNTIL level greater than 100/0[250/0 ADV]in at least one9.b 10.12.15.d.16.d.17.RNO 19.d.and 20.b.21.RNO 26.27.29.31.a RNO MAINTAIN Intact S/G narrow range levels between 20%[25%ADV]and 50%.MONITOR pressurizer

PORVs and block valves: MONITOR AC busses energized from start busses.MONITOR Res pressure greater than 300 psig.MAINTAIN core exit TICslessthan target temperature.(if ruptured S/G pressure dropping)MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):*MAINTAIN ReS cool down rate less than 10QJF/hr, CONTINUE ReS depressurization

UNTIL any of following conditions

satisfied:

  • Both of the following:

1)ReS press less than ruptured S/G pressureAND

2)Pressurizer

Jevel greater than 10%[20%ADV]OR*Pressurizer

level greater than 650/0 OR*ReS subcooling

based on core exit TICs less than 4CfF.(if ReS pressure dropping)MONITOR for indication

of leakage from pressurizer

PORV.CONTROL charging flow to maintain pressurizer

level.MONITOR ECCS flow NOT required: a.ReS subcooling

based on core exit TICs greater than 40 of b.Pressurizer

level greater than 10%[20%ADV].MONITOR if letdown can be established.(pzr level greater than 20%[35°10 ADV])WHEN ReS pressure is less than 700 psig t THEN ISOLATE CLAs.Page 1f of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 HANDOUT Page 3 of 3 STEP ACTION 32.CONTROL ReS pressure and charging flow to minimize RCS-to-secondary

leakage: RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL RISING LEVEL DROPPING GREATER THAN 84%[80%ADV]AND STABLE PZRLEVEL*RAISE charging*RAISE charging*RAISE charging Less than 20%flow.flow.flow.[35%AD\/]*DEPRESSURIZE

  • MAINTAIN ReS Res USING and Ruptured S/G(s)Substep 32.b.pressures equal.PZRLEVEL*DEPRESSURIZE
  • TURN ON*MAINTAIN ReS Between Res USING pressu rizer heaters.and Ruptured S/G(s)200/0[35%ADV]Substep 32.b.pressures equal.andPZR LEVEL*REDUCE charging*TURN ON*MAINTAIN ReS Between flow.pressu rizer heaters.and Ruptured S/G(s)50%and 650/0*DEPRESSURIZE

pressures equal.RCSUSING Substep 32.b.Greater than 65%*REDUCE charging*TURN ON*MAINTAIN ReS flow.pressurizer

heaters.and Ruptured S/G(s)pressures equal.32.c.MONITOR ReS pressure less than 1040 psig.34.MONITOR if containment

spray should be stopped.(pressure less than 2.0 psig)35.MONITOR if containment

vacuum control should be returned to normal: (less than 1.0 psig).38.MAINTAIN pressurizer

at saturation

temperature

for ruptured S/G pressure USING pressurizer

heaters.41.MONITOR Rep status.(Rep#2 funning)41.a.4)MONITOR natural circulation (if NO Rep can be started).RNO 42.MONITOR if source range channels should be reinstated.(lRM flux less than 10-4%)42.t WHEN shutdown monitor ALARM LEDs darkAND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.[M13]Page 19 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 1.0 PURPOSE This procedure provides actions to terminate leakage of reactor coolant into the secondary system following a steam generator tube rupture.2.0 SYMPTOMS AND ENTRY CONDITIONS

2.1 ENTRY CONDITIONS

E-O Reactor Trip or Safety Injection:

  • Secondary radiation.
  • S/G level rising in an uncontrolled

manner.E-1, ES-1.2, and ECA-2.1 Foldout Page*S/G level rising in an uncontrolled

manner..E-1 ES-1.2 E-2 ES-3.1 ES-3.2 ES-3.3 Loss of Reactor or Secondary Coolant:*Secondary radiation.

  • S/G level rising in an uncontrolled

manner.Post LOCA Cooldown and Depressurization:

  • S/G level rising in an uncontrolled

manner.Faulted Steam Generator Isolation:

  • Secondary radiation.

Post-SGTR Cooldown Using Backfill:*S/G level rising in an uncontrolled

manner..Post-SGTR Cooldown Using Slowdown:*S/G level rising in an uncontrolled

manner.Post-SGTR Cooldown Using Steam Dump:*S/G level rising in an uncontrolled

manner.(continued

on next page.)Page 2 of 41

SQN STEAM G.ENERA TOR TUBE RUPTURE E..3 Rev.17 2.1 ENTRY CONDITIONS (Continued)

ECA-2.1 ECA-3.1 ECA-3.2 ECA-3.3 FR-H.3 Uncontrolled

Depressurization

of All Steam Generators:

  • Secondary radiation.

SGTR and LOCA-Subcooled Recovery:*S/G fevel rising in an uncontrolled

manner.SGTR and LOCA-Saturated Recovery:*S/G level rising in an uncontrolled

manner.SGTR Without Pressurizer

Pressure Control:*S/G level rising in an uncontrolled

manner.*Pressurizer

pressure control restored.Steam Generator High Level:*Secondary Radiation.

3.0 OPERATOR ACTIONS Page 3 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17[STEP I I ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED NOTE This procedure has a foldout page.1.MONITOR at least one Rep RUNNING.IF all Reps are STOPPED, THEN PERFORM the following:

a.SUSPEND monitoring

ruptured loop T-cold indication

on PTS status tree.b.WHEN step 32 is completed OR E-3 is exited J THEN RESUME monitoring

ruptured loop T-cold indication

on PTS status tree.2.MONITOR Rep trip criteria: a.CHECK the following:

a.GO TO Step 3.*ReS pressure less than 1250 psig..........

AND*At least one CCP OR 81 pump RUNNING.b.STOP Reps.Page 4 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 3.MONITOR indications

of Ruptured S/G(s): a.IDENTIFY Ruptured S/G(s)as indicated by any of the following:

  • Unexpected

rise in any S/G narrow range level.OR*High radiation from any S/G sample.OR*RADCON survey of main steam Jines and S/G blowdown lines.OR*High radiation on any main steamline radiation monitor.II RESPONSE NOT OBTAINED a.WHEN Ruptured S/G(s)identified, THEN PERFORM Steps 4 through 8.GO TO Step 9.Page 5 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-317 I STEP 11 ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED CAUTION Isolating both steam supplies to the TO AFW pump when it is the only source of feed flow will result in loss of secondary heat sink.*4.ISOLATE flow from Ruptured 8/G(s): 8.ADJUST Ruptured S/G(s)atmospheric

relief controller

setpoint to 87%in AUTO.(1040 psig)b.CHECK Ruptured S/G(s)atmospheric

relief hand switch in P-AUTO and valve(s)CLOSED.c.CLOSE TD AFW pump steam supply from Ruptured S/G FCV-1-15 (S/G#1)or FCV-1-16 (3/G#4).b.WHEN Ruptured S/G(s)pressure less than 1040 psig, THEN PERFORM the following:

1)VERIFY atmospheric

relief CLOSED.2)IF atmospheric

relief NOT closed, THEN CLOSE atmospheric

relief.IF Ruptured S/G(s)atmospheric

relief CANNOT be closed, THEN DISPATCH personnel to close atmospheric

relief USING EA-1-2, Local Control of S/G PORVs.c.IF at least one MD AFW pump running, THEN ISOLATE steam to TD AFW pump USING FCV-1-17 or FCV-1-18.IF TO AFW pump is still running, THEN DISPATCH operator to locally close steam supply from ruptured S/G FCV-1-15 or FCV-1-16.[West Valve Vault Room]d.VERIFY Ruptured S/G(s)blowdown d.CLOSE valve(s).isolation valves CLOSED.(Step continued on next page.)Page 6 of 41

SQN STEAM GENERATOR TUBe RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 4.e.CLOSE Ruptured S/G(s}MSIV and MSIV bypass valve.e.PERFORM the following:

1)CLOSE Intact S/G MSIVs and MSIVbypassvalves.

2)DISPATCH operator to perform EA..1-1, Closing MSIVs Locally, for any MSIV or MSIV bypass valve which fails to close.3)ISOLATE steam header: PLACE condenser steam dumps in OFF.[M-4]*ENSURE steam dump valves CLOSED.[M-4]CLOSE FCV--47-180, HP steam Seal Supply Isolation.

[M-2]*ENSURE FCV-47-181

HP Steam Seal Supply Bypass CLOSED.[M-2]CLOSE MSR HP steam supply isolation varves.[M-2]DISPATCH operator to locally isolate steam header USING EA-1-4, Local Isolation of Steam Header in Turb Bldg.4)USE Intact S/G(s)atmospheric

relief for steam dump.IF any Ruptured S/G CANNOT be isolated from at least one Intact S/G, THEN GO TO ECA-3.1, SGTR and LOCASubcooled Recovery.-------Page 7 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED CAUTION Feeding a S/G that is Faulted and Ruptured increases the potential for an uncontrolled

ReS cooldown and S/G overfill.This option should NOT be considered

UNLESS needed for Res cooldown.5.MONITOR Ruptured S/G(s)level: a.CHECK narrow range level greater than 10%[25%ADV].b.WHEN ruptured S/G level is greater than 10%[25%ADV], THEN PERFORM the following:

1)STOP feed flow to ruptured S/G.2)ENSURE Turbine Driven AFW LeV for ruptured S/G in CLOSE PULL TO LOCK.a.MAINTAIN feed flow to Ruptured S/G UNTIL level greater than 10%[25%ADV].Page 8 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 6.VERIFY Ruptured S/G ISOLATED from Intact S/G(s): I J RESPONSE NOT OBTAINED 7.a.CHECK either of the foUowing conditions

SATISFIED:

  • Ruptured S/G MSIVs and MSIV bypass valves CLOSED OR*MSIV(s)and MSIV bypass valve(s)CLOSED on Intact S/G(s)to be used for ReS cooldown.b.CHECK S/G#1 or S/G#4 ruptured.c.CHECK TDAFW pump steam supply from ruptured S/G ISOLATED:*FCV-1-15 (S/G#1)or FCV-1-16 (S/G#4)CLOSED CHECK Ruptured S/G pressure greater than 550 psig (Unit1)or 425 psig (Unit 2).a.DO NOT CONTINUE this procedure UNTIL one of conditions

satisfied.

b.GO TO Step 7.c.DO NOT CONTINUE this procedure UNTIL ruptured S/G steam supply isolated by one of the following:

  • FCV-1-15 (S/G#1)or FCV-1-16 (S/G#4)CLOSED OR*FCV-1-17 or FCV-1-18 CLOSED OR*TDAFW pump TRIPPED.GO TO ECA-3.1, SGTR andSubcooled Recovery.----.----IlPage 9 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP](ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED NOTE Blocking low steamline pressure SI as soon as pressurizer

pressure is less than 1960 psig will prevent an inadvertent

MSIV closure and keep condenser available for steam dump.*After the low steamline pressure 81 signal is blocked, main steamline isolation will occur if.the high steam pressure rate setpoint is exceeded.*The 1250 psig Rep trip criterion is NOT applicable

after ReS cooldown is initiated in the following step.8.INITIATE ReS cooldown: a.DETERMINE target core exit TIC temperature

based on Ruptured S/G pressure: Lowest Ruptured Target Core Exit S/G pressure (psig)TiC Temp (OF)1100 or greater 497 1050-1099 492 1000-1049 486 950-999 480 900-949 473 850-899 467 800-849 460 750-799 453 700-749 445 650-699 437 600-649 428 550-599 419 500-549 410 450-499 399 425-449 393 (Step continued on next page.)Page 10 of41

SQN STEAM GENERATOR TUBE RUPTURE E-317 I STEP II ACTION/EXPECTED

RESPONSE 8.b.WHEN Res pressure less than 1960 psig, THEN PERFORM the following:

1)BLOCK low steamline pressure SL 2)CHECK STEAMLINE PRESS ISOUSI BLOCK RATE ISOL ENABLE permissive

LIT.[M-4A, A4]c.DUMP steam to condenser from Intact S/G(s)at maximum achievable

rate: 1)CHECK condenser available:

  • C-9 condenser interlock permissive

LIT.[M-4A, E6]*Intact S/G MSIVs OPEN.2)PLACE steam dumps in OFF.3)ENSURE steam dumps in steam pressure mode with demand less than 25%k 4)PLACE steam dumps in ON.5)ADJUST steam dump demand to FULLY OPEN three cooldown valves.6)WHEN T-avg is tess than 540°F, THEN BYPASS steam dump interlock.

II RESPONSE NOT OBTAINEDIF steam dumps NOT available)

THEN OPEN atmospheric

relief valves for Intact S/G(s)RAISE AFW flow to intact S/Gs as necessary to support cooldown.IF local control of atmospheric

reliefs is necessary, THEN DISPATCH personnel to dump steam at maximum achievable

rate USING EA-1-2, Local Control of S/G PORVs.IF NO Intact S/G available, THEN PERFORM the following:

  • USE Faulted S/G.OR*GO TO ECA-3.1)SGTR and LOCA-Subcooled Recovery.-------7)RAISE AFW flow to intact S/Gs as necessary to support cooldown.(Step continued on next page.)Page 11 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 8.d.WHEN core exit TICs less than target temperature

determined

in Substep 8.a, THEN PERFORM the following:

1)CLOSE steam dumps or S/G atmospheric

reliefs to stop cooldown.2)REDUCE AFW flow as necessary to stop cool down.MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10%[25 0 ft, ADV]in at least one Intact S/G.3)MAINTAIN core exit TICs less than target temperature

USING steam dumps or atmospheric

reliefs.II RESPONSE NOT OBTAINED Page 12 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 9.MAINTAIN Intact S/G narrow range levels: a.Greater than 10%[25%ADV]b.Between 20%[25%ADV]and 50%.II RESPONSE NOT OBTAINED a.MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10%[25%ADV]in at least one Intact S/G.IF at least 440 gpm AFW flow CANNOT be established, THEN ESTABLISH main feedwater or condensate

flow USING Establishing

Secondary Heat Sink Using Main Feedwater or Condensate

System b.IF level in any Intact S/G continues to rise in an uncontrolled

manner, THEN STOP ReS cool down and GO TO Step 1.--_..Page 13 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 (STEPII ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED CAUTION Any time a pressurizer

PORV opens, there is a possibility

that it may stick open.10.MONITOR pressurizer

PORVs and block valves: a.Power to block valves AVAILABLE b.Pressurizer

PORVs CLOSED c.At least one block valve OPEN.a.DISPATCH personnel to restore power to block valves USING EA-201-1 , 480 V Board Room Breaker Alignments.

b.IF pressurizer

pressure less than 2335 psig, THEN CLOSE pressurizer

PORVs.IF pressurizer

PORV CANNOT be closed, THEN CLOSE its block valve.IF pressurizer

PORV remains open AND associated

block valve CANNOT be closed, THEN GO TO ECA-3.1 , SGTR and LOCA-Subcooled Recovery.---.----c.OPEN one block valve UNLESS closed to isolate an open PORV.Page 14of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 11.RESET 81 signal.12.MONITOR AC busses energized from start busses.13.ENSURE Phase A and Phase B RESET.II RESPONSE NOT OBTAINED ENSURE diesel generators

supplying shutdown boards.WHEN shutdown power restored, THEN ENSURE safeguards

equipment running as necessary.

14.CHECK control air established

to containment:

[Panel 6K and 6L]*1-FCV-32-80

(2-FCV-32-81)

Train A essential air OPEN*1-FCV-32-102

(2-FCV-32-103)

Train B essential air OPEN*1-FCV-32-110

(2-FCV-32-111)

non-essential

air OPEN.ESTABLISH control air to containment

USING EA-32-1, Establishing

Control Air to Containment.

Page 15 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 15.DETERMINE if RHR pumps should be stopped: a.CHECK RHR pump suction aligned from RWST.b.CHECK ReS pressure greater than 300 psig.c.STOP RHR pumps and PLACE in A-AUTO.d.MONITOR ReS pressure greater than 300 psig.II RESPONSE NOT OBTAINED a.GO TO Step 16.b.GO TO Step 16..c.IF pump(s)CANNOT be stopped in A-AUTO t THEN PLACE affected RHR pump(s)in PULL TO LOCK.d.IF ReS pressure dropping uncontrolled, THEN START RHR pumps.Page 16 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 16.CHECK if Res cooldown should be stopped: 8.CHECK core exit TICs less than target temperature

determined

in Substep 8.a.b.CLOSE steam dumps or atmospheric

reliefs to stop cooldown.c.REDUCE AFW flow as necessary to stop cooldown..MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 1 0%[25%ADV]in at least one Intact S/G.d.MAINTAIN core exit TICs less than target temperature

USING steam dumps or atmospheric

reliefs.II RESPONSE NOT OBTAINED 8.DO NOT CONTINUE this procedure UNTIL core exit TICs less than target temperature.

Page 17 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 17.CHECK Ruptured S/G(s)pressure STABLE or RISING.18.CHECK ReS subcooling

based on core exit TICs greater than 60°F.II RESPONSE NOT OBTAINED MAINTAIN pressure of Intact S/Gs used for cooldown at least 250 psi below ruptured S/G(s):*SLOWLY DUMP steam from Intact S/Gs*MAINTAIN Res cooldown rate less than 1 GO°F/hr.IF Intact S/G(s)used for cooldown CANNOT be maintained

at least 250 psi below ruptured S/G(s)r THEN GO TO ECA-3.1 t SGTR and LOCA...Subcooled Recovery.---..---GO TO ECA-3.1, SGTR andSubcooled Recovery.---.-----Page 18 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 19.DEPRESSURIZE

Res to minimize break flow and to refill pressurizer:

a.CHECK normal pressurizer

spray

b.INITIATE maximum available pressurizer

spray.c.CHECK depressurization

rate ADEQUATE.d.CONTINUE depressurization

UNTIL any of thefollowingconditions

SATISFIED:

  • Both of the following:

1)ReS pressure less than Ruptured S/G(s)pressure AND 2)Pressurizer

level greater than 10%[20%ADV].OR*Pressurizer

level greater than 65%.OR*Res subcooling

based on core exit TICs less than 40°F.I

NOT OBTAINED a.GO TO Cautions prior to Step 20.c.GO TO Cautions prior to Step 20.(step continued on next page)Page 19 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSEII RESPONSE NOT OBTAINED 19.e.CLOSE spray valve(s): 1)Normal spray valves.1)STOP Reps#1 and 2.IF ReS pressure continues to drop, THEN STOP additional

Rep as necessary.

2)Auxiliary spray valves.2)ISOLATE auxiliary spray line.f.GO TO Caution prior to Step 22.=--Page 20 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 , STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED CAUTION*Depressurizing

the ReS using a pressurizer

PORV may cause PRT rupture with resulting abnormal containment

conditions.

  • Excessive cycling of a pressurizer

PORV increases the potential for PORV failure.NOTE Upper head voiding may occur during ReS depressurization

if no Reps are running.This may result in rapidly rising pressurizer

level.20.DEPRESSURIZE

ReS USING one pressurizer

PORV to minimize break flow and to refill pressurizer:

a.CHECK at least one pressurizer

PORV AVAILABLE 8.PERFORM the following to establish auxiliary spray: 1)ENSURE at least one SI pump RUNNING.IF NO 81 pump running, THEN GO TO ECA-3.3, SGTR Without Pressurizer

Pressure Control.---.---2)ENSURE at least one CCP RUNNING.3)CLOSE CePIT inlet valves FCV-63-39 and FCV-63-40.

4)CLOSE CePIT outlet valves FCV-63-25 and FCV-63-26.

5)OPEN charging line isolation valves FCV-62-90 and FCV-62-91.

6)ESTABLISH auxiliary spray USING EA-62-4 r Establishing

Auxiliary Spray.(step continued on next page)Page 21 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 20.a.(Continued)

b.OPEN one pressurizer

PORV UNTIL any of the following conditions

SATISFIED:

  • Both of the following:1)ReS pressure less than Ruptured S/G(s)pressure AND 2)Pressurizer

level greater than 10%[200/0 ADV].OR*Pressurizer

level greater than 650/0.OR*ReS subcooling

based on core exit TICs less than 40°F.IF auxiliary spray established, THEN GO TO Step 19.b.

IF auxiliary spray CANNOT be established, THEN GO TO ECA-3.3, SGTR Without Pressurizer

Pressure Control.---..-----(step continued on next page)Page 22 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 20.c.CLOSE pressurizer

PORV.c.CLOSE block valve.d.CLOSE spray valve(s): 1)Normal spray valves 1)STOP Reps#1 andIF ReS pressure continues to drop.THEN STOP additional

Rep as necessary.

I-2)Auxiliary spray valves.2)ISOLATE auxiliary spray line.21.CHECK ReS pressure RISING.CLOSE pressurizer

PORV block valve.IF pressure continues to drop, THEN PERFORM the following:

1)MONITOR the following conditions

for indication

of leakage from pressurizer

PORV:*Acoustic Monitoring

System*Tail pipe temperatures

PRT indications.

2)GO TO ECA-3.1, SGTR andSubcooled Recovery.--------Page 23 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED CAUTION Any delay in terminating

51 after termination

criteria are met may cause Ruptured S/G(s)overfilL 22.CHECK if ECCS flow should be terminated:

a.ReS subcooling

based on core exit a.GO TO ECA-3.1 , SGTR and LOCA-TICs greater than 40°F.Subcooled Recovery.*b.Secondary heat sink: b.IF neither condition satisfied J THEN*Narrow range level GO TO ECA-3.1, SGTR and LOCA-in at least one Intact S/G Subcooled Recovery.greater than 10%[25%ADV]..OR*Total feed flow to S/Gs greater than 440 gpm AVAILABLE.

c.ReS pressure STABLE or RISING.c.GO TO ECA-3.1, SGTR and LOCA-Subcooled Recovery...Pressurizer

level d.GO TO Step 6.greater than 10%[20 0 h ADV].:e-Page 24 of 41

SQN STEAM GENERATOR TUBE RUPTURE E..317 I STEPII ACTION/EXPECTED

RESPONSE 23.STOP the following ECCS pumps: a.STOP 81 pumps and PLACE in A-AUTO.b.CHECK offsite power supplying shutdown boards.c.STOP all BUT one CCP and PLACE in A-AUTO.24" ISOLATE CePIT: 8.CLOSE inlet isolation varves FCV-63-39 and FCV-63-40.

b.CLOSE outlet isolation valves FCV-63-26 and FCV-63...25.II RESPONSE NOT OBTAINED a.IF any 81 pump(s)CANNOT be stopped in A-AUTO, THEN

in PULL TO LOCK.b.ENSURE one CCP in PULL TO LOCK.GO TO Step 24.c.IF CCP CANNOT be stopped inA-AUTO, THEN ENSURE one CCP in PULL TO LOCK.IF cePIT flowpath CANNOT be isolated from MeR, THEN CLOSE affected CePIT valves USING EA-201-3, Operation of Motor..Operated Valves from Outside MeR.Page 25 of 41

SQN STEAM GENERATOR TUBE RUPTURE E*3 Rev.17 I STEP)I ACTION/EXPECTED

RESPONSE 25.ESTABLISH charging flow: a.CLOSE seal water flow control valve FCV-62-89.

b.OPEN charging flow isolation valves FCV-62-90 and FCV-62-91.

G.ENSURE normal or alternate charging isolation valve FCV-62-86 or FeV-62-8S OPEN.d.ESTABLISH desired charging flow USING seal water and charging flow control valves FCV-62-89 and FCV-62-93.

26.CONTROL charging flow to maintain pressurizer

level.II RESPONSE NOT OBTAINED b.IF power available, THEN OPEN affected valve from Rx MOV Board USING EA-201-3, Operation of Motor-Operated

Valves from Outside MeR.Page 26 of 41

SQN STEAM GENERATOR TUBE RUPTURE E..3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 27..MONITOR ECCS flow NOT required:ReS 5ubcooling

based on core exit T/Cs greater than 40 0 F.b.Pressurizer

level greater than 10%[200/0 ADV].II RESPONSE NOT OBTAINED a.ESTABLISH ECCS flow manually by performing

one or both.of the following:

  • ESTABLISH CePIT flow as necessary USING App..C.*START CCPs or 81 pumps manually as necessary.

GO TO ECA-3..1, SGTR and LOCASubcooled Recovery.---.---b.CONTROL charging flow to maintain pressurizer

level.IF pressurizer

level CANNOT be maintained, THEN PERFORM the following:

1)ESTABLISH ECCS flow manually by performing

one or both of the following:

  • ESTABLISH CePIT flow as necessary USING App.C.*START CCPs or 81 pumps manually as necessary.

2)GO TO

SGTR and LOCA...Subcooled Recovery.---..-.......Page 27 of 41

SQN STEAM GENERATOR TUBE RUPTURE Rev.17 I STEP II ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED 28.CHECK veT makeup control system: a.Makeup set for greater than ReS boron concentration.

b.Makeup set for automatic control.ADJUST controls as necessary.

29.MONITOR if letdown can be established:

a.CHECK pressurizer

level greater than 20 0 k[35%ADV].b.ESTABLISH letdown USING EA-62-5, Establishing

Normal Charging and Letdown.a.GO TO Step 30.b.ESTABLISH excess letdown USING EA-62-3, Establishing

Excess Letdown..Page 28 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17[STEP II ACTION/EXPECTED

RESPONSE 30.DETERMINE if CCP suction can be aligned to VeT: a.CHECK CCP suction ALIGNED to RWST.b.ENSURE VCT level is greater than 20%.c.OPEN VeT outlet valves LCV-62-132

and LCV-62-133

and PLACE in PULL A-P-AUTO.d.CLOSE RWSTvalves

LCV-62-135

and LCV-62-136

and PLACE in PULL A-P-AUTO.e.ENSURE VeT cover gas established

USING EA-O-8, Establishing

VeT Cover Gas.II RESPONSE NOT OBTAINED a.IF ECCS pumps aligned for sump recirculation, THEN EVALUATE terminating

sump recirculation

USING EA-63-6, Terminating

Sump Recirculation.

GO TO Step 31.Page 29 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 31.DETERMINE if CLAs should be isolated: a.CHECK ReS pressure less than 700 psig.b.CHECK the following:

  • ReS subcooling

based on core exit TICs greater than 40°F*Pressurizer

level greater than 10%[20%ADV].II RESPONSE NOT OBTAINED a.WHEN ReS pressure is less than 700 psig, THEN PERFORM Substeps 31.b, C J and d.GO TO Step 32.b.GO TO ECA-3.1, SGTR and LOCA...Subcooted Recovery.---....-....I 1 p-c.CHECK power to CLA isolation valves c.DISPATCH personnel to restore AVAILABLE.

power to CLA isolation valves USING EA-201...1, 480 V Board Room Breaker Alignments.

d.CLOSE CLA isolation valves.d.IF power available to affected valve(s), THEN CLOSE affected valve(s)USING EA-201-3 J Operation of Motor-Operated

Valves from Outside MeR.IF any CLA valve CANNOT be closed, THEN VENT unisolated

CLA(s)USING EA-63-1 1 Venting Unisolated

Cold Leg Accumulator.

Page 30 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 32..CONTROL Res pressure and charging flow to minimize RCS-to-secondary

leakage: a.PERFORM appropriate

action(s)from table:]I RESPONSE NOT OBTAINED RUPTURED S/G RUPTURED S/G RUPTURED S/G LEVEL LEVEL LEVEL RISING DROPPING GREATER THAN 84%[800/0 ADV]AND STABLE PZR LEVEL Less than 200/0*RAISE charging RAISE charging*RAISE charging[35%ADV]flow.flow.flow.*DEPRESSURIZE

  • MAINTAIN ReS Res USING and Ruptured Substep 32.b.S/G(s)pressures equal.Between DEPRESSURIZE

TURN ON MAINTAIN ReS 20%[350/0 ADV]Res USING pressurizer

heaters.and Ruptured andSubstep 32.b.S/G(s)pressures equal.Between*REDUCE charging TURN ON MAINTAIN ReS 50%and 65%flow.pressurizer

heaters.and Ruptured*DEPRESSURIZE

S/G(s)pressures RCSUSING equal.Substep 32.b.Greater than 65%REDUCE charging TURN ON MAINTAIN ReS flow.pressurizer

heaters.and Ruptured S/G(s)pressures equal..(step continued on next page)Page 31 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 32.b.USE normal pressurizer

spray as required by SUbstep 32.a.c.MONITOR ReS pressure less than 1040 psig.33.CHECK at least one Rep RUNNING.I[RESPONSE NOT 081 AINED b.IF letdown in service l THEN ESTABLISH auxiliary spray USING EA-62-4, Establishing

Auxiliary Spray.IF letdown NOT in service OR auxiliary spray CANNOT be established, THEN USE onepressurizerPORV.

c.PERFORM the following:1)MAINTAIN ReS subcooling

based on core exit TICs greater than 40°F.2)DEPRESSURIZE

ReS USING Substep 32.b.UNTIL Res pressure less than 1040 psig.3)MAINTAIN ReS and Ruptured S/G(s)pressures less than 1040 psig.RESUME monitoring

ruptured loop T-cold indication

on PTS status tree..Page 32 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 J STEP I J ACTION/EXPECTED

RESPONSE I'RESPONSE NOT OBTAINED 34.MONITOR if containment

spray should be stopped: 8.CHECK any containrnent

spray pump a.GO TO Step 35.RUNNING.=--b.CHECK containment

pressure b.GO TO Step 35.less than 2.0 psig.=--c.CHECK containment

spray suction c.NOTIFY TSC to determine aligned to RWST.when one or both trains of cntmt spray should be stopped.WHEN directed by TSC, THEN PERFORM Substeps 34.d through 34.f.GO TO Step 35.=--d.RESET Containment

Spray signal.e.STOP containment

spray pumps and PLACE in A-AUTO.f.CLOSE containment

spray discharge valves FCV-72-2 and FCV-72-39.

Page 33 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 35.MONITOR if containment

vacuum control should be returned to normal: a.CHECK containment

pressure less than 1.0 psig.b.ENSURE containment

vacuum relief isolation valves OPEN:[Panel 6K or M-9]*FCV-30-46*FCV-30-47*FCV-30-48.

36.DETERMINE if diesel generators

should be stopped: a.VERIFY shutdown boards ENERGIZED from start busses.II RESPONSE NOT OBTAINED a.GO TO Step 36.=--a.ATTEMPT to restore offsite power to shutdown boards USING EA-202-1, Restoring Offsite Power to 6900 V Shutdown Boards.*1 b.STOP any unloaded diesel generators

and PLACE in standby USING EA-82-1, Placing DIGs in Standby.Page 34 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev, 17 I STEP II ACTION/EXPECTED

RESPONSE 37.DISPATCH personnel to perform EA-O-3 J Minimizing

Secondary Plant Contamination.

38.MAINTAIN pressurizer

liquid at saturation

temperature

for ruptured S/G pressure:*OPERATE pressurizer

heaters as necessary.

II RESPONSE NOT OBTAINED 39.CHECK Rep cooling NORMAL:*Rep CCS flow*Rep seal injection flow.ESTABLISH cooling to Reps USING EA-68-3, Establishing

Rep Cooling.Page 35 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 III ACTION/EXPECTED

RESPONSE 40.DETERMINE jf Rep seal return flow should be established:

a.VERIFY Rep seal injection flow established.

b.VERIFY CCS cooling to seal water heat exchanger NORMAL:*SEAL WATER HX OUTLET FLOWITEMP ABNORMAL alarm DARK.[M-27B-B, A6 (M-27B-D, A7)].c.ENSURE the following:

  • VeT pressure greater than 13 psig.[M-6]*RCDT pressure[O-L-2]less than VeT pressure.d.OPEN seal return isolation valves FCV-62-61 and FCV-62-63.

II RESPONSE NOT OBTAINED a.GO TO Step 41.b.ESTABLISH CCS cooling to seal water heat exchanger.

IF CCS cooling to seal water heat exchanger CANNOT be established, THEN GO TO Step 41.c.GO TO Step 41.Page 36 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP I I ACTION/EXPECTED

RESPONSE II RESPONSE NOT OBTAINED CAUTION NOTE Loss of all Rep seal cooling may cause Rep seal damage and will require a TSC status evaluation

prior to restarting

affected Reps.Loop 2 Rep and associated

spray valve will provide adequate spray flow for Res pressure control.If Loop 2 is not available, all three remaining Reps may be required to ensure adequate spray flow" 41.MONITOR Rep status: a.CHECK Rep#2 RUNNING.a.ATTEMPT to start Rep(s)to provide normal pzr spray: 1)IF all Rep seal cooling has preViously

been lost l THEN NOTIFY TSC to initiate Rep restart status evaluation.

2)IF RVLIS upper range indication

less than 104%, THEN PERFORM the following:

RAISE pressurizer

level to greater thanOR until level stops rising..RAISE ReS subcooling

based on core exit TICs to greater than 76°F.OPERATE pzr heaters as necessary to raise pzr liquid temperature

to saturation.

3)ESTABLISH conditions

for starting RCP(s)USING EA-68-2, Establishing

Rep Start Conditions.(step continued on next page)Page 37 of 41

SQN STEAM GENERATOR TUBE RUPTURE E*3 Rev.17 I STEPII ACTION/EXPECTED

RESPONSE 41.(Continued)

b.STOP RCP(s)NOT needed for normal pressurizer

spray.I, RESPONSE NOT OBTAINED 4)IF Rep start conditions

established, THEN START Rep#2 (if available)

OR Reps#1" 3 t and 4.IF NO Rep can be started, THEN MONITOR natural circulation

USING EA-68-6, Monitoring

Natural Circulation

Conditions.

IF natural circulation

CANNOT be verified, THEN RAISE steam dump rate.Page 38 of41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 42.MONITOR if source range channels should be reinstated:

a.CHECK intermediate

range flux less than 10-4%power on operable channels.b.CHECK source range channels REINSTATED.

c.SELECT one SRM and one IRM on NR-45 recorder.d.ENSURE audio count rate operation.

e.RESET shutdown monitor alarm setpoints.

[M-13]f.WHEN shutdown monitor ALARM LEOs dark AND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL.[M-13]43.SHUT DOWN unnecessary

plant equipment:

REFER TO O-GO..12, Realignment

of Secondary Equipment Following ReactorlTurbine

Trip.II RESPONSE NOT OBTAINED a.GO TO Step 43.b.REINSTATE source range channels by simultaneously

placing both SRM TRIP RESET-BLOCK

switches to RESET position.[M-4]Page 39 of 41

SQN STEAM GENERATOR TUBE RUPTURE E-3 Rev.17 I STEP II ACTION/EXPECTED

RESPONSE 44.PERFORM EA-O-9, Post Trip Administrative

Requirements

and Recovery Actions.II RESPONSE NOT OBTAINED NOTE Backfill method is slow but preferred since it minimizes radiological

releases and facilitates

processing

of contaminated

reactor coolant.Slowdown method is slow but minimizes radiological

releases and eliminates

boron dilution and secondary chemistry effects on ReS.Steam dump method is fast but may involve ra dialogical

releases and water hammer concerns (if water exists in the steamlines).

45.DETERMINE appropriate

post-SGTR cooldown method: a.SELECT appropriate

procedure:

ES-3.1, Post-SGTR Cooldown Using Backfill.OR ES-3.2, Post-SGTR Cooldown Using Slowdown.OR*ES-3.3, Post-SGTR Cooldown Using Steam Dump.b.GO TO selected procedure.

--_l1li"---

END Page 40 of41

SQN STEAM GENERATOR TUBE RUPTURE APPENDIX C ESTABLISHING

CePIT FLOW E-3 Rev.17 Page 1 of 1 1.ENSURE CCP suction aligned to one of the following:

  • RWST with level greater than 27°j{, OR*RHR pump discharge USING ES-1.3, Transfer to RHR Containment

Sump.2.CLOSE charging flow isolation valves FeV-52-S0 and FCV-62-91.

3.OPEN CePIT outlet valves FCV...63-26 and FCV-63-25.

4.OPEN CePIT inlet valves FCV-63-39 and FCV-63-40.

END OF TEXT Page 41 of 41 o o o o o

PR*EPAREDI

REVISED BY: JPM 22-AP2 Page 1 of 18 Rev 3 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE

MEASURE B.1.f JPM 22-AP2 CALIBRATE POWER RANGE NUCLEAR INSTRUMENTATION

Date/VALIDATED BY:*APPROVED BY: (Operations

Training Manager)Date/Date!CONCURRED:

    • (Operations

Representative)

Date/*Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM,or individual

step changes that do not affect the flow of the JPM.**Operations

Concurrence

required for new JPMs and changes that affect the flow*of the JPM (if not driven by a procedure revision).

JPM 22-AP2 Page 2 of 18 Rev 3 I NUCLEAR TRAINING REVISION/USAGE

LOG REVISION DESCRIPTION

OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 Created from JPM 22.Y 8/2/04 All MG Croteau 1 Updated References

N 10/5/05 All JJ Tricoglou 2 Updated References.

Minor format N 2/15/07 All RH Evans changes.3 Added detail to steps and standards Allv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.

JPM 22-AP2 Page 3 of 18 Rev 3 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE

MEASURE Task: Calibrate the Power Range Nuclear Instrumentation

JAITA task:#0150050201

KIA Ratings: 015000 A 1.01 (3.5-3.8)015020 G13 (3.3-3.6)(RO)015020 G9 (3.4-3.3)015000 A4.02(3.9-3.9)Task Standard: 1)EaCh channel of Power Range instrumentation (on its power range"A" drawer)will indicate within acceptance

'criteria tolerances

of the calorimetric.

2)The unit is not tripped by a power range neutron flux rate trip.Evaluation

Method: Simulator__X__In-Plant---===================================================================================

Performer:

Performance

Rating: SAT Evaluator:

NAME UNSAT SIGNATURE Performance

Time DATE Start Time---Finish Time------===================================================================================

COMMENTS

JPM 22-AP2 Page 4 of 18 Rev 3 SPECIAL INSTRUCTIONS

TO EVALUATOR:

1.Sequenced steps identified

by an"s" 2.AnyUNSAT requires comments 3.This task is to be performed using the simulator in IC#16.[Rx Power should be100 0/0]4.MANUALLY ADJUST N-41 and N-43 power to between 100.5 and 101.00/0.ENSURE all other NIS reactor power indications

are between 99.5 and 100.50/0.5.Ensure operator performs the following required actions for SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.27 min Local__

Tools/Equipment/Procedures

Needed: 0-SI-OPS-092-078.0, Sections 3.0, 6.1,6.2, Appendix D References:

l-itle Rev No, 1.0-SI-OPS-092-078.0

Power Range Neutron Flux Channel Calibration

By 18 Heat Balance Comparison

====================="============================================

READ TO OPERATOR Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understandyourassigned

task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.The unit is at steady state conditions

with all NIS channels and LEFM operable.INITIATING

CUES: 1.You are theCRO and the US has directed you to perform.O-SI-OPS-092-078.0.

2.Section 4.0 of 0-SI-OPS-092-078.0

has been completed.

3.Notify the US when the Sihas been completed and any necessary adjustments

have been made.

Job Performance

Checklist STEP/ST ANDARD JPM 22-AP2 Page 5 of 18 Rev 3 SAT/UNSAT STEP 1.: Obtain the appropriate

procedure.

SAT UNSAT STANDARD: Operator identifies

O-SI-OPS-092-078.0and

goes to section 6.0"Performance".COMMENTS: STEP 2.:[1]VERIFY availability

of LEFM calorimetric

power:[aj CHECK

s.tatus NO:Rf\{AL:Ctn ICS{NSSS.and BOP}CUrT*:'ot Calcritnetrrc

Data s.cre;e.:rL

"{ESo 0[bI CHECK LEFfs{Core Themlal Pewer (ICS point 0211,s)

{gre'en)data.YES N{)o[c]CHEC.K LEFrit1lv1FVV

he,ader te:rrq:<*<rature

{ICS point T85C2M.A.)

greater

or equai to 2SD:::Fv YES N:Q a STANDARD: Operator pulls up LEFM ICS screen and points, then annotates procedure that LEFM calorimetric

power is available.

COMMENTS: Start Time__SAT UNSAT

Job Performance

Checklist STEP/ST ANDARD STEP 3.:[2]IF LEFM calorimetric

power NOT available OR ICScomputer

NOT available, THEN....PERFORtA the

Ie]IF LEFM

power CANNOT be rest.ored in tirT:i:e to OOP1:lplete

this

THEN'PERFOR'".the

....:1.: R.EDUGE reactor

(341*1 ()i1VJt).or;'ess U.S1NG V t 11-8{if d"iaHah4e}

orN:;SA 2..:WHE\N reactor

is less*

THEN CONTINUE this.

'U*s;in:g alternate power in d5cati ens as 5.p;<JE<c::me(i

be!kt\Y.STANDARD: Operator marks the 4 sub steps (a, b, c.1,&c.2)N/A because the LEFM was determined

to be available in the previous step.COMMENTS: JPM 22-AP2 Page 6 of 18 Rev 3 SAT/UNSAT SAT UNSAT

Job Performance

Checklist sTEP/sT ANDARD STEP 4.:[3]DETERMINE reactor core power level by performing

the applicable

appendix below.RCS AT greater.and A CJ LE F't1:CJC*re the:rm:3il (U211,B).avajlabre'

{step (1]

criteria r;l:E:t)RGS ATbetw*een

and 4D%.and:6 a LE F}t1-(;SDre tnennal (U211

av*ailabtE'

xG.ST grea,:er than

C Cl LEF't.1:core

pC{ttef (:U2118)N::DT a'Jailab4e

but tcs

U1118 is available RG.S AT 9lreater than

[)Cl lCS corE: therrnaI pCtl.i"er indic:aiicn (U1 t tS and U2t tEl NOT

AND RECORD below the (N/A power if using printout from ICS)0/0 Rated Core Thermal Power=0/0 Cue: Inform the operator that the ICS printer is not available.

Cue: If candidate asks if the engineering

procedure O-PI-SXX-OOO-022.2

has been performed, state that it has not been performed.

STANDARD: Operator determines

Appendix A.is applicable

to determine the reactor power level.COMMENTS: JPM 22-AP2 Page 7 of 18 Rev 3 sAT/U N SAT SAT UNSAT

Job Performance

Checklist STEP/STANDARD

EVALUATOR NOTE: The following steps are from Appendix A.STEP 5.:[1]ENSURE S/G blowdown flows are updated by performing

the following functions onlCS:[a]SELECT"NSS&BOP".[b]SELECT"CALORIMETRIC

FUNCTION MENU".[c]SELECT"UPDATE OPERATOR ENTERED SLOWDOWN FLOW" P;8RFORtAone

0:1 the falhrrt#lfrt:Q

opbonnot used)1IF using:CC411puter

if 2:26: tAl SiG T o1:a!§Slo¥/dcvln

flo'vi, THEt4 fa)'VERlfY

v-a.:j::!j':E

is.updLa'bng (chang;:iniQ

vaiktes)..(b)If

po:j::nt is. ulpdatingL

J T:HE.N NO TIFY}t1 that pc:int is nc4 upda.tlrtg

c;nd inltia1eVVCt

..('a]RECORD

fo;!SIG

fktVI:: JPM 22-AP2 Page 8 of 18 Rev 3 SAT/U N SAT SAT UNSAT[ReS LOOP 2 3 4 BLO:WI)O\'VN

flOW

FI-1i-"164

j Ib]i E:t4 SU RE

uDvrs.above entered ICS..VIAIT a minirnun1 e:f to minut.es to allow prograrTl b,:;a.ccurately

Jialue..Cue: The blowdown flow point is updating and manual blowdown flows are not required.STANDARD: Operator determines

blowdown flow is updating and marks substeps 1 b, all of substep 2 N/A.COMMENTS:

JPM 22-AP2 Page 9 of 18 Rev 3 Job Performance

Checklist STEP/ST AN*DARD STEP 6.:[2]SELECT"DISPLAY CURRENT CALORIMETRIC

DATA" on ICS Calorimetric

menu AND PERFORM one of the following:

SAT/UNSAT SAT UNSAT_____M\¥t._----OR*rbl P\RlNT po\ver ie'V"'el a:nd

AND*ATTACH re[fl*Oft to th@s instnJ'ctJcn.

Cue: Inform the operator that the printer is not available.

STANDARD: Operator records U2118 and U1127 values.COMMENTS: EVALUATOR NOTE: The operator should transistion

back to section 6.1 at the completion

of Appendx A.The following steps are from Section 6.1.STEP 7.:[4]RECORD"AS FOUND" power level from each of the four NIS A Channel drawers.P'OW:EjRRAN*GE

CHANt*rEt

():,

1\r4-42

)

{X.I-@:2-a001B)

N-44 tX:I-2i2-5GrTIf6;B

J

N.'IS POl.VER t.%}: SAT UNSAT STANDA*RD:

Operator records NIS power range readings from the A channel drawers on 1-M-13 on1-XI-92-5005B,50068, 50078, and 50088 COMMENTS:

Job Performance

Checklist STEP/STANDARD

STEP 8.:[5]COMPARE NIS indication

with core thermal power level.[a]CHECK appropriate

box to indicate whether the followingfound" ACCEPTANCE

CRITERIA were satisfied.

ACCEPTAN,CE

CRITERiA: The indicatedNlS

power le'tel recorded i:n st$p[4]is equal10 the core thermal: pewer

recorded iin step{31 as W-s*tedon the wtihin+/-2.0

JPM 22-AP2 Page 10 of 18 Rev 3 SAT/UNSAT SAT UNSAT NJSGhanneoI

N-41 NmSChannet

N4.2 N:::S Channe*;l N-43 N:::S Channe:i N*-44 YES Cl o o o filA a a Q: Q: STANDARD: Operator CHECKS to determine if NIS channels are within2%.Then, Checks YES for all NIS channels.COMMENTS: STEP 9.:[b]IF any NIS channels were inoperable

during the performance

of this instruction, THEN: NOTIFY applicable

unit SRO that this SI must be performed on all inoperable

NIS channels when they are returned to service.SAT UNSAT STANDARD: Since all were operable per the initiating

conditions, the operator marks this substep N/A.COMMENTS: STEP 10.:[6]VERIFY that all NIS channel indications

are within+/-3 percent of the determined

core thermal power level.YES NO Q a STAN.DARD:

Operator checks the YES*box.COMMENTS: SAT UNSAT

Job Performance

Checklist STEP/ST AN DARD JPM 22-AP2 Page 11 of 18 Rev 3 SAT/UNSAT STEP 11.:[7]IF a NIS channel was more than 3 percent in error in the non--SAT conservative

direction (core thermal>NIS)THEN NOTIFY Engineering

to determine if the calibration

error-UNSAT impacts operability

of the NIS high flux trip.STANDARD: Operator marks this step N/A.COMMENTS: STEP 12.:[8]CHECK appropriate

box to indicate whether the following"as-found"-SAT acceptance

criteria were satisfied:

-UNSAT ACCEPTANCE

CRITERIA: The indicated NIS power level recorded in step[4]is less than or equal to 100.5 percent.YES NO NIA N::1S*C;n,.anne::[

N*-41 Q:0 Q Ni:iS e,ho*anne':;

N**-42 U:Q Q N::[SChanne{

N-43 Q:0 Q

N*-4.;0'Q Q STANDARD: The operator checks NO forN-41 and N-43 and checks YES for other 2 channels.COMMENTS: STEP 13.:[9]IF any channel does not meet acceptance

criteria, OR NIS Channel-SAT adjustment

is desired ,THEN PERFORM adjustment

of section 6.2-UNSAT AND/OR REDUCE reactor power not to exceed 100 percent.STANDARD: Operator continues on to section 6.2.COMMENTS:

Job Performance

Checklist STEP/STANDARD

JPM 22-AP2 Page 12 of 18 Rev 3 SAT/UNSAT EVALUATOR NOTE: The following steps are from Section 6.2-SAT STEP 14.:[1]IF calculated

average power in Section 6.1 or on printed copy and differs by more than 30/0 from average RCS delta T, THEN-UNSAT NOTIFY Engineering

to determine the cause.STANDARD: Operator determines

calculated

average power and average delta T does not differ by more than 3%by comparing calculated

average power against delta T from ICS or use 1-M-5 delta T instruments

and N/As this step.COMMENTS: STEP 15.:[2]VERIFY reactor power has remained constant0.5%)since-SAT performance

of section 6.1.-UNSAT STANDARD: Operator ensures power has remained stable since he/she took the readings.COMMENTS: STEP 16.:[3]IF NIS power range channel is inoperable

-SAT THEN REQUEST Instrument

Maintenance

to Bypass inoperable

NIS channel in-UNSAT accordance

with O-PI-IXX-092-001.0.

STANDARD: Operator N/As this step since aU power range instruments

are operable.COMMENTS: STEP 17.:[4]ENSURE all NIS power range channels are operable or bypassed with no-SAT bistables tripped.-UNSAT STANDARD: Operator verifies no bistables tripped bymonitoringTrip

status panel, 1-XX-55-5, bistable lIights on 1-M-5.(Initial conditions

had all channels operable)COMMENTS:

Job Performance

Checklist STEP/ST AN DARD JPM 22-AP2 Page 13 of 18 Rev 3 SAT/UNSAT STEP 18.:[5]ENSURE rod control system is in MANUAL in accordance

with 0-SO-85-1-SAT-UNSAT STANDARD: Operator turns

0, ROD CONTROL MODE SELECTOR, to the MANUAL position.Should refer to

A laminated sheet is available.

COMMENTS: Evaluator Note: Procedure contains a note stating Steps[6J ,through[9J must be completed on one NIS channel before proceeding

to the next channel.Operator must adjust the N-41'and N-43, may choose to adjust all 4 channels.STEP 19.:[6]IF rate trip exists'(or occurs)on the NIS channel being calibrated, THEN-SAT CLEAR that channels trip signal (momentarily

set RATE MODE switch to-UNSAT RESET position)and annunciator

XA-55-6A,."NC-41U or NC-41K NIS POWER RANGE HIGH NEUTRON FLUX RATE," before proceeding

to the next NIS channel.'Trip Cleared Ni,A.N

0 NlSGhanne,*

N-42 U 0 Critical Step N is Ghann

Q;Q

N-44 0:0 STANDARD: Operator verifies NO rate trip signals are inon ANY of the PR and the annunciator

is clear.*CRITICAL PORTION: If rate trip occurs the operator resets it prior to continuing

to the next channel.COMMENTS:

Job Performance

Checklist STEP/STANDARD

STEP 20.:[7]ADJUST gain potentiometer

on associated

channel's power range B drawer to bring that channel's indicated power level to within+/-..5%of the calorimetric

power recorded in section 6.1 or listed on the printed copy.AND JPM 22-AP2 Page 14 of 18 Rev 3 SAT/UNSAT N-41 adjustment

SAT NJS

N41 N ISChanne;;

ti-42 Gh*anne*§N-4.3 ENSURE gain

latch re-engaged.

__J4.djusiment

Required a a a a CI Q U Q UNSAT N-43 adjustment

SAT STANDARD: Operator must adjust N41 and N43 to satisfy criteria.The operator should repeat the above step prior to adjusting the second PRo (only the bold portion of the standard is critical)COMMENTS: STEP 21.:[8]IF fine gain potentiometer

on power range B drawer will not provide enough adjustment

to satisfy the calibration

requirements

of step[7], THEN REQUEST Instrument

Maintenance

to adjust the coarse gain (resistor R312, Coarse Level Adjust)inside the applicable

power range drawer, AND READJUST fine gain potentiometer

to achieve calibration

requirements

specified in step[7].UNSAT Critical StepiSChannefi

t4-41: N

N-42 lSCih.anne*ili

t4-43: N lSChanne1 N-44 It,djustrrtent

Reql1!ired

o o o o STANDARD: Operator marks step as N/a because the fine gain will provide the needed adjustment.

COMMENTS:

Job Performance

Checklist STEP/STAN DARD STEP 22.:[9]IF additional

NIS channel(s)

require calibration, THEN RETURN to step[6]Evaluator note: Procedure step f6]is JPM step 19 STANDARD: Operator may return to step[6]to adjust either N41 or N43 or other 2 channels if desired.After adjustments

to Nls is complete, the operator continues to the next step COMMENTS: STEP 23.:[10]WHEN NI*S adjustments

have been completed, THEN RECORD the"as left" power level from NIS power range channels.POWER RA:NGE

CH,ANN.El NIS POJ'/ER (£>/.3}

(;\J-92-5000'8:)

CXJ-92-5007B)

NJ-44 tXi-Q2-5008B

J STANDARD: Operator records the readings from each of the 4 PR Nls.COMMENTS: STEP 24.:[11]IF NIS power range*channel is inoperable, THEN REQUEST Instrument

Maintenance

to remove Bypass on inoperable

NIS channel in accordance

with O-PI-IXX-092-001.0.

STANDARD: Operator NIAs this step since all Nls are operable.COMMENTS: JPM 22-AP2 Page 15 of 18 Rev 3 SAT/UNSAT N-41 adjustment

SAT_UNSAT N-43 adjustment

SAT UNSAT SAT UNSAT SAT UNSAT

Job Performance

Checklist STEP/ST AN DARD JPM 22-AP2 Page 16 of 18 Rev 3 SAT/UNSAT STEP 25.:[12]CHECK appropriate

box to indicate whether the following"as left"-SAT acceptance

criteria were satisfied.

-UNSAT ACCEPTAN:CE

CHITERlA.:

T.he indrc.ated

N IS patNer leve!: recorded in step (1 OJ is wrthin+/-0".5 percent the: cal*oMfmeftrk:

p-o'werieve!

lreoorded in SectonG.1 01'a:s Jisted en the printed copy.YES NlA NWS

N-41 Cl a Q 1-'-.ns Channe:t N-42 U:Q Q Ni:;S ChanneJ N-43 Q Q Q Nl\tS

N-44.a:QSTANDARD: Operator checks YES box for N41, N42, N43,&N44, all being within:!:..5%(of 1 00%).COMMENTS: STEP 26.:[13]IF acceptance

criteria were NOT satisfied for any NIS channel, THEN-SAT NOTIFY Shift Manager that acceptance

criteria were'NOT met and another performance

of this test is necessary,-UNSAT subsequently

action 2 of LCO 3.3.1.1 (Unit 1)orLCO 3.3.1 (Unit 2)must be satisfied if the other performance

does not meet acceptance

criteria.STANDARD: Operator N/As this step.COMMENTS: STEP 27.:[14]RETURN rod control system to AUTO in accordance

with O-SO-85-1.

-SAT Cue: When operator acknowledges

the 3 minute wait in the note preceding the-UNSAT step, Inform the operator that 3 minutes have elapsed.STANDARD: Operator places control rod bank selector"switch

to the AUTO after waiting at least 3 minutes for signal to decay.Should refer to O-SO-85-1.

A laminated sheet is available.

COMMENTS:

Job Performance

Checklist STEP/ST AN DARD JPM 22-AP2 Page 17 of 18 Rev 3 SAT/UNSAT STEP 28.: Notify SRO that the NIS channels have been calibrated.

SAT STANDARD: Operator notifies the SRO that the SI has been completed and all power range nuclear instruments

have been adjusted to meet the acceptance

criteria.COMMENTS: END of JPM UNSAT Stop Time__

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION

OF TASK)DIRECTION TO TRAINEE: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating

cues and reports on other actions when directed by you.Ensure you indicate tome when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIO.NS:

The unit is at steady state conditions

with all NIS channels and LEFM operable.INITIATING

CUES: You are the CRO and the US has directed*you to perform 0-SI-OPS-092-078.0.

Section 4.0 of 0-SI-OPS-092-078.0

has been completed.

Notify the US when the 51 has been completed and any necessary adjustments

have been made.

...'""""....................." 1..1'....'...-...,'_"'..-..............

........--..__-.._.__---.-..:.__**_---TV AN STANDARD PROGRAMS AND PROCESSES SURVEILLANCE

TEST PROGRAM , r l SURVEILLANCE

TASK SHEET (STS)Page 1 of 1 SPP-8.2 Date 06-04*2004

Page 25 of 29 SURVEILLANCE

TASK SHEET (ST5)Page Work Order SI Key----,.p.....

'1 Procedure No.0

j Y!1v Title

.

11/Perf.Section\J t , I O.fi.:.>/*r"1/1 il T est Reason

t\(J";",'-;" c:...

Data Sheets--------------i1.I/Due-----.....-.----------i!

V'Extension

rv1ax.Extension--------------!l

Frequency-----------..---,;.....;,-.--!l

EO--------------11

ASME Xl APP Mode--------------11

Performance

il

Operational

Condition

Dry Cask Storage O*Yes 0 No Subsequent

Reviews--------------il

Instruction'

of C (!xl-/pg'ALN'I Dat'e Time Start Date Time Completion

Date Time Test Director/lead

Performer Date (ASME Xl Sis require review within

96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />).Date Time Independent

Reviewer Date ANII (If required).Date Remark:.,-Copy of STS sent to Scheduling

Initials Date Section No.Men Our.Hrs Section No.Men Our.Hrs Our.Hrs I Our.Hrs SPP-8.2-1[06.04-200

4 1 No.Men No.Men.

!Section k__-Se-eu-*oo---i.Page 1 of 1.TVA 40753[06-20041

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE

INSTRUCTION

O-SI-OPS-092-078.0

POWER'RANGE NEUTRON FLUX CHANNEL CALIBRATION

BY HEAT BALANCE COMPARISON

Revision 18 QUALITY RELATED w.T.LEARY PREPARED/PROOFREAD

BY:

RESPONSI BLE ORGAN IZA TION:_O.;;...;p

.......

O__.N..;;..",;;;,S

_KEITH PERKINS APPROVED BY:-------.---------------

EFFECT'IVE

DATE:03/30/06

LEVEL OF USE: CONTINUOUS

USE REVISION DESCRIPTION:

Revised to add a.note.directing

that consistency

between channels be considered

when determining

if adjust is desired.This is a minor change.THIS PROCEDURE COULD AFFECT REACTIVITY.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

CHANNEL CALIBRATION

BY Rev: 18 1&2 HEAT BALANCE COMPARISON

Page 2 of 33 TABLE OF CONTENTS Page 1 of 2 Section Title Page TABLE OF CONTENTS 2 1.0 INTRODUCTION

4 1.1 Purpose 4 1*.2 Scope 4 1.2.1 Surveillance

Test to be Performed 4 1.2.2 Requirements

Fulfilled 4 1.2.3 Modes 4 1.3 Frequency and Conditions

4 2.*0 REFERENCES*

5 2.1 Performance

  • References

5 2.2 Developmental

References

5 3.0 PRECAUTIONS

AND LIMITATIONS

5 4..0 PREREQUISITE

ACTION*S.....................................*........................................................

7 4.1 Preliminary

Actions 7 4.2 Measuring a*nd Test Equipment, Parts, and Supplies 7 4.3 Field Preparations

7 4.4 Approvals and Notifications

7 5.0 ACCEPTANCE

CRITERIA 7

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

CHANNEL CALIBRATION

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Page 3 of 33 TABLE OF CONTENTS Page 2 of 2 Section Title Page 6.0 PERFORMANCE

.8 6.1 As-Found Data 8 6.2 NIS Channel Adjustment

14 7.0 POST PE.RFORMANCE

ACTIVITY 18 APPENDICES

APPENDIX A: APPENDIX B: APPENDIX C: APPENDIX D: CALCULATION

OF CORE THERMAL POWER LEVEL USING LEFM 19 SUBSTITUTION

OF RCS AT LOW POWER LEVELS

WITH LEFM NOT AVAILABLE)

22 CALCULATION

OF CORE THERMAL POWER LEVEL USING U1118 (>40%WITH LEFM NOT AVAILABLE)

23 CALCULATION

OF CORE THERMAL POWER LEVEL WITH PLANT COMPUTER INOPERABLE (RCST GREATER THAN 400/0)26 SOURCE NOTES 33

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

CHANNEL CALIBRATION

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Page 4 of 33 1.0 INTRODUCTION

1.1 Purpose This Surveillance

Instruction (SI)provides detailed steps for ensuring proper calibration

of the power range neutron flux channels.1.2 Scope 1.2.1 Surveillance

Test to be Performed This Instruction

performs a comparison

between the power level calculated

by the Nuclear Instrumentation

System (NIS)power range neutron flux channels and the"true" power level as determined

by a secondary system heat balance based value.If necessary, the power range channels are adjusted to agree with the"true" power level.This instruction

also verifies availability

of Leading Edge Flow Meter (LEFM)calorimetric

power.1.2.2 Requirements

Fulfilled Performance

of this Instruction

completely

fulfills Technical Specification (TS)Surveillance

Requirement (SR)4.3.1.1.1.8.2 (Table 4.3-1, item 2, note 2)and Technical Requirements

Manual (TR)4.3.3.15.1.

1.2.3 Modes A.Applicable

Mode-1 (above 15 percent power).B.Performance

Mode-1 (above 15 percent power).1.3*Frequency and Conditions

This test must be performed at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the reactor power level is greater than 15 percent.[C.3]To ensureNIS accuracy, this test should be performed when directed by O-GO-4 or O-GO-5.In the event that the Plant Computer is unavailable, provisions

have been incorporated

in this procedure to fulfill the SR requirements.

[C.5]

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

CHANNEL CALIBRATION

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Page 5 of 33 2.0 REFERENCES

2.1 Performance

References

O-PI-SXX-OOO-022.2, Calorimetric

Calculation.(Optional)

2.2 Developmental

References

A.SQN Technical Specifications.

B.SPP-8.1, Conduct of Testing C.NP-STD-4.4.7, Attachment

1, Writer's Guide for Technical Documents D.0-PI-NUC-092-082.0, Post Startup NIS Calibration

following Core Load.E.Memo from Reactor EngineeringRIMS S57 941219 934 F.Integrated

Computer System Critical Design Requirements

and Operator's

Guide.3.0 PRECAUTIONS

AND LIMITATIONS

A.Reactor power must remain constant (+/-0.5°/0)during the performance

of Sections 6.1 and 6.2.Itis desirable for any required NIS adjustment

be made promptly during performance

of these sections.B.Average ReS temperature (T avg)should be maintained

within 0.5°F of RCS reference temperature (Tref)'C.Caution should be exercised when adjustingNIS

power range instrumentation

to minimize the potential for a channel trip.D.Only one NIS channel shall be adjusted at a time.If a rate trip occurs, the channel's trip signal and annunciator

on panel XA-55-6A,"NC-41 U or NC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RATE" must be cleared before proceeding

to the next NISchannel.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

CHANNEL CALIBRATION

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Page 6 of 33 3.0 PRECAUTIONS

AND LIMITATIONS (Continued)

E.Operations

and Engineering

should be notified if larger than normal channel adjustments (as determined

by the SRO)are required to bring the power range channels into alignment with calculated

core thermal power.[C.4]An operability

concern may exist if excessive error in the non-conservative

direction adversely impacts the NIS high flux trip setpoint.The 3%tolerance for calibration

error on the high flux trip setpoints was selected using the extrapolated

error from the 30%power level.F.The reactor cores have been loaded with a low leakage-loading pattern which can affectNIS Reactor Power level indications

such that differences

greater than the Acceptance

Criteria can occur between NIS and true power level.The impact of the NIS non-linearity

due to low leakage loading pattern isin the conservative

direction, since NISindicated

power rises faster than true power during a power increase.0-GO-5 may direct performance

of this procedure to ensure excessive errors in the non-conservative

direction do not exist.During plant restarts, Reactor Engineering

may perform 0-PI-NUC-092-082.0

at 40/0 power to provide an initial NIS correction

for startup.G.Technical Specifications

require aheatbalance

calculation

for adjustment

of theNIS when the Plant is above 15%power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.If the Leading Edge Flow Meter (LEFM)is available, ICS point U2118 is required to be used for the heat balance when greater than 15%power (TRM 3.3.3.15).

If LEFM is NOT available, then LoopT data should be used between 15 and 40%power due to potential inaccuracies

in the feedwater-flow venturi heat balance below 40%.If LEFM is NOT avai-Iable

above 40%, then venturi-based

calorimetric

power (U1118)should be used.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

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Page 7 of 33 J I Unit------4.0 PR"EREQUISITE

ACTIONS Date)'X b!.!.rIiJ(NOTE During the performance

of this Instruction, any"IFITHEN" statement may be marked N/A when the corresponding

stated condition does not OCCUL 4.1 Preliminary

Actions[1]ENSURE Instruction

to be used is a copy of effective version_()Il and Data Package Cover Sheet is attached.!'J{;-4.2 Measuring and Test Equipment, Parts, and Supplies None;4.3 Field Preparations

[1]ENSURE reactor power and RCS average temperature

are stable.4.4 Approvals and Notifications

[1]NOTIFY SRO of test performance.

5.0 ACCEPTANCECRITERIA

A.The indicated"as-found" power level from each operable NIS neutron flux channel must equal the core thermal power level to within+/-2.0%.B.The indicated"as-left" power level from each operable NIS neutron flux channel that was adjusted must equal the core thermal power level to within+/-0.5%.c.If the criteria stated above are NOT satisfied, the SRO shall be notified and Action Requirement

2 of TS Table 3.3-1 satisfied.

D.LEFM shall be used for the plant calorimetric

measurement

for power range NIS calibration

by heat balance comparison.

If this criteria is NOT satisfied, the SRO shall be notified and the applicable

action of TRM 3.3.3.15 shall be entered.

SQN POWER RANGE NEUTRON FLUX

0 CHANNEL CALIBRATION

BY Rev: 18 1&2 HEAT BALANCE COMPARISON

Page 8 of 33 Unit------6.0 PERFORMANCE

6.1 As-Found Data Date-----NOTE 1 NOTE 2 The following step determines

if LEFM is available tosatisfyTRM

3.3.3.15.If LEFM is NOT available, operators should notify US, document status and continue with next step.Main feedwater temperature

must be greater than or equal to 250°F for reliable LEFM data.[1]VERIFY availabi-lity

of LEFM calorimetric

power:[a]CHECK LEFM status NORMAL on ICS (NSSS and BOP)Current Calorimetric

Data screen.YES NO o 0[b]CHECK LEFM Core Thermal Power (ICS point U2118)showing good (green)data.YES NO o 0[c]CHECK LEFM MFW header temperature-(ICS point T8502MA)greater than or equal to 250°F.YES NO o 0 ACCEPTANCE

CRITERIA: LEFM is available based upon the indications

above.

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

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Page 9 of 33 Unit------6.1 As-Found Data Date-----NOTE With LEFM unavailable, AFD limit lines in COLR must be made more restrictive

by 1%and Rod Insertion Limit lines in COLR must be raised by 3 steps.These adjustments

are automatically

applied in ICS.[2]IF LEFM calorimetric

power NOT available OR ICS computer NOT available, THEN PERFORM the following:

[a]ENTER applicable

action of TRM 3.3.3.15.[b]ENSURE work order initiated as required.[c]IF LEFM calorimetric

power CANNOT be restored in time to complete this surveillance, THEN PERFORM the following:

1.REDUCE reactor power to 98.7°1b (3411 MWt)or less USING U1118 (if available)

orNIS.2.WHEN reactor power is less than 98.7%, THEN CONTINUE this instruction

using alternate power indications

as specified below.

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0

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Page 10 of 33 Unit------6.1 As-Found Data Date-----NOTE If Engineering

has performed 0-PI-SXX-000-022.2, then the applicable

section{s)of

0-PI-SXX-OOO-022.2

may be used in place of Appendix C orO to obtain the current calorimetric

power.[3]DETERMINE reactor core power level by performing

the applicable

appendix below: CONDITION APPENDIX../ReS L1 T greater than 15'%and A 0 LEFM core thermal power (U2118)available (step[1]acceptance

criteria met)RCS L1 T between 15%

and B 0 LEFM core thermal power (U2118)NOT available RCS L1 Tgreater than 40%C 0 LEFM core thermal power (U2118)NOT available but ICS point U1118 is available RCS L1 T greater than 400/0 and D 0 ICS core thermal power indication (U1118 and U2118)NOT available AND RECORD below (N/A power if using printout from ICS):%Rated Core Thermal Power=-----

SQN POWER RANGE NEUTRON FLUX

CHANNEL CALIBRATION

BY Rev: 18 1&2 HEAT BALANCE COMPARISON

Page 11 of 33 Unit------6.1 As-Found Data (Continued)

Date-----NOTE Data for an inoperable

NISchannelmay

be marked N/A.[4]RECORD"as-found" power level from each of the four NIS power range A channel drawers: POWER RANGE" AS-FOUND" CHANNEL NIS POWER (°10)N-41 (XI-92-5005B)

N-42 (XI-92-5006B)

N-43 (XI-92-5007B)

N-44 (XI-92-5008B)

NOTE The following step is performed to satisfy Tech Specs.[5]COMPARE NIS indication

with core thermal power level.[a]CHECK appropriate

box to indicate whether the following"as-found" acceptance

criteria were satisfied:

ACCEPTANCE

CRITERIA: The indicated NIS power level recorded in step[4]is.equal to the core thermal power level recorded in step[3]or as listed on the printed copy to within+/-2.0 percent.YES NO N/A NIS Channel N-41 0 0 0 NIS ChannelN-42

0 0 0 NIS Channel N-43 0 0 0 NIS Channel N-44 0 0 0 RO orSRO

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0

CHANNEL CALIBRA TIONBY Rev: 18 1&2 HEAT BALANCE COMPARISON

Page 12 of 33 Unit------Date-----6.1 As-Found Data (Continued)

[b]IF any NIS channels were inoperable

during the performance

of this Instruction, THEN NOTIFY applicable

unit SROthat this SI must be performed on all inoperable

NIS channels when they are returned to service.[6]VERIFY that all NIS channel indications

are within+/-3 percent of the determined

core thermal power level.YES o NO o[7]IF a NIS channel was more than 3 percent in error in the non-conservative

direction (core thermal power>NIS), THEN NOTIFY Engineering

to determine if the calibration

error impacts operability

of the NIShigh flux trip.[8]CHECK appropriate

box to indicate whether the following"as-found" acceptance

criteria were satisfied:

ACCEPTANCE

C.RITERIA:

The indicated NIS power level recorded in step[4]is less than or equal to 100.5 percent.YES NO N/A NIS ChannelN-41

0 0 0 NIS Channel N-42 0 0 0 NIS Channel N-43 0 0 0 NIS Channel N-44 0 0 0 RO or SRO

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0

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Page 13 of 33 Unit

6.1 As-Found Data (Continued)

Date-----NOTE Consistency

between the four NIS PR channels is to be considered

when determining

if an adjustment

is desired.[9]IF any channel does not meet acceptance

criteria, OR NIS Channel Adjustment

is desired,THEN

PERFORM adjustment

using section 6.2 AND/OR REDUCE reactor power not to exceed 100 percent.END OF TEXT

SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0

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Page 14 of 33 Unit------6.2 NIS Channel Adjustment

Date-----NOTE 1 Performance

of this section is required only for those PR*channels designated

by the Reactor Operator or that did not satisfy the acceptance

criteria in Section 6.1.All other NISchannels

may be marked N/A.NOTE 2 During the performance

of Section 6.2, data required for an inoperable

NIS channel may be marked N/A.[1]IF calculated

average power in Section 6.1 or on printed copy differs by more than 3%from average ReS delta T, THEN NOTIFY Engineering

to determine the cause.[2]VERIFY reactor power has remained constant (+/-0.5%)since performance

of Section1.NOTE The inoperable

channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance

testing of other channels.[3]IF NIS power range channel is inoperable, THEN REQUEST Instrument

Maintenance

to Bypass inoperable

NIS channel in accordance

with 0-PI-IXX-092-001.0.

[4]ENSURE all NIS power range channels are operable or bypassed with no bistables tripped.[5]ENSURE rod control system is in MANUAL in accordance

with 0-SO-85-1.D

SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0

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Page 15 of 33 Unit------6.2 NIS Channel Adjustment (Continued)

Date-----NOTE 1 Steps[6]through[9]must be completed on one NIS channel before proceeding

to the next channel.NOTE 2 NIS channels in the following step may be performed outof sequence.[6]IF a rate trip exists (or occurs)on the NIS channel being calibrated, THEN CLEAR that channels trip signal (momentarily

set RATE MODE switch to RESET position)and annunciator

on panel XA-55-6A,"NC-41UorNC-41

K NIS POWER RANGE HlGH NEUTRON FLUX RATE," before proceeding

to the next NIS channel.NIS Channel N-41 NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 Trip Cleared o o o o N/A o o o o First Person-------CV_NOTE The gain potentiometers

have latches which must be disengaged

prior to adjustment, and re-enga*ged

following adjustment.

[7]ADJUST gain potentiometer

on associated

channel's power range B drawer to bring that channel's*

indicated power level to within+/-0.5%of the calorimetric

power recorded in Section 6.1 or as listed on the printed copy.AND ENSURE gain potentiometer

latch re-engaged.

[C.2]Adjustment

Required N/A NIS Channel N-4100 NIS Channel N-4200 NISChannel

N-4300 NIS Channel N-4400 First Person_CV-

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Page 16 of 33 Unit------Date

6.2 NIS.Channel Adjustment (Continued)

[8]IF fine gain potentiometer

on power range B drawer will not provide enough adjustment

to satisfy the calibration

requirements

of step[7], THEN REQUEST Instrument

Maintenance

to adjust the coarse gain (resistor R312, Coarse Level Adjust)inside the applicable

power range drawer, AND N/A o o o o NIS Channel N-41 NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 READJUST fine gain potenti'ometer

to achieve calibration

requirements

specified in step-[7].Adjustment

Required o o o oFirstPersonCV--------,.-

[9], IF additional

NIS channel(s)

require calibration, THEN R*ETURN TO step-[6].[10]WHEN NIS adjustments

have been completed, THEN RECORD"as-left" power level from NIS power range channels.POWER RANGE" AS-LEFT" CHANNEL NIS POWE*R (%)N-41 (XI-92-5005B)

N-42 (XI-92-5006B)

N-43 (XI-92-5007B)

N-44 (XI-92-5008B)

First Person_IV_

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Page 17 of 33 Unit------6.2 NIS Channel Adjustment (Continued)

[11]IF NIS power range channel is inoperable, THEN REQUEST Instrument

Maintenance

to remove Bypass on inoperable

NIS'channel in accordance

with 0-PI-IXX-092-001.0.

[12].CHECK appropriate

box to indicate whether the foHowing"as-left" acceptance

criteria were satisfied.

Date-----ACCEPTANCE

CRIT:ERIA:

The indicated NIS power level recorded in step[10]is within+/-O.5 percent the calorimetric

power level recorded in Section 6.1 or as listed on the printed copy.NIS Channel N-41 NIS Channel N-42 NIS Channel N-43 NIS Channel N-44 YES o o o o NO o o o o RO or SRO N/A o o o o[13]IF accepta.nce

criteria were NOT satisfied for any NIS channel, THEN NOTIFY Shift Manager that acceptance

criteria were NOT met and another performance

of this test is necessary, subsequently

action 2 of LCO 3.3.1.1 (Unit 1)or LCO 3.3.1 (Unit 2)must be satisfied if the other performance

does not meet acceptance

criteria.NOTE NIS channel adjustment

may cause step change in input to rod control.A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.[14]RETURN Rod Control System to AUTO in accordance

with 0-SO-85-1.

END OF TEXT D

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Page 18 of 33 7.0 POST PERFORMANCE

ACTIVITY[1]NOTIFY SRO that test has been completed.

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Page 19 of 33 Unit---Date---NOTE 1 NOTE 2 APPENDIX A Page 1 of 3 CALCULATION

OF CORE THERMAL POWER USING LEFM ICS allows two options for blowdown flows: Option#1 (Preferred)-use point[F2261.A]which requires no operator entered data (computer automatically

updates the blowdown flows)*.Option#2-use manually enteredS/G

blowdown flow rates.Computer point[F2261Alis

more accurate than flow indicators

located in the fan rooms.If the computer point is inoperable

and blowdown flows from the FIS's are used, then indicated core thermal power may be a slightly differentvalue.

[1]ENSURE S/G blowdown flows are updated by performing

the following functions on ICS:[a]SELECT"NSSS AND BOP".[b]SELECT"CALORIMETRIC

FUNCTION MENU".[c]SELECT"UPDATE OPERATOR ENTERED BLOWDOWN FLOW" on menu AND PERFORM one of the following options (N/A option not used): 1.IF using computer point[F2261Al S/G Total Blowdown Flow, T*HEN (a)VERIFY point value is updating (changing values).(b)IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WOo D D D D D

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Page 20 of 33 Unit---Date---NOTE APPENDIX A Page 2 of 3 Local readings of steam generator blowdown flow are obtained from Panel L-357.2.IF manually updating blowdown flows, THEN[a]RECORD local readings for S/G blowdown flow: RCS SLOWDOWN FLOW LOOP (GPM)1 FI-1-152 2 FI-1-156 3 FI-1-160 4 FI-1-164[b]ENSURE blowdown flows above entered in ICS.[c]IF blowdown flows were updated, THEN WAIT a m*inimum of 10 minutes to allow program to accur.ately

reflect new value.D

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Page 21 of 33 Unit APPENDIX A Date Page 3 of 3 NOTE ICS printout may be used to documentpower

level and NIS values.Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used)and the printed sheet value (if used).SI acceptance

is satisfied in the body of the instruction.

[2]SELECT"DISPLAY CURRENT CALORIMETRIC

DATA" on ICS Calorimetric

menu AND PERFORM one of the following:

[a]RECORD the following:

LEFM Core Thermal Power (U2118)Percent Rated Core Thermal Power (U 1127)OR Mwt---_-----.

0/0-----D[b]PRINT power level and NIS'values AND ATTACH report to this instruction.

D

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Page 22 of 33 Unit---Date-_--:.--NOTE 1 NOTE 2 APPENDIX B Page 1 of 1 SUBSTITUT*ION

OF RCS i\T AT lOW POWER LEVELS40%WITH LEFM NOT AVAILABLE)

RCS delta T loops

are aligned to results of a secondary-side

heat balance.Consequently, using i\Ts to adjust NIS at.Iow power levels still satisfies the requirement

to use heat balance.Loop i\T is used to avoid potentially

non-conservative

errors in NIS power range indication

if adjustments

were made based upon an inaccurate

secondary heat balance at a*low feedwater flowrate.At low power levels the traditional

seco*ndary-side

heat balance (U 1118)is not as accurate as Reactor Coolant LoopT'8.This appendix should NOT be used if LEFM is operable.[1]CALCULATE the average RCSdelta T using control board indications

or computer point for average RCSLoop A (TI-68-2D)

°/0 PLANT COMPUTER Loop B (TI-68-25D)

°/0 OR U0485Loop C (TI-68-44D)

°/0 Loop D

°/0 Total°/0-;-(4)=Avg[2]RECORD average RCS delta T as the core thermal power level 0/0.°/0

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Page 23 of 33 Unit---Date---APPENDIXC Page 1 of 3 CALCULATION

OF CORE-THERMAL POWER LEVEL USING U1118 (>40%WITH LEFM NOT AVAILABLE)

NOTE 1 NOTE 2 NOTE 3 This appendix is used when RCS L1 T is greater than 40%and LEFM (U2118)NOT available, butlCS and U 1118 are available.

ICSallows two options for blowdown flows: Option#1 (Preferred)

-use point[F2261A]which requires no operator entered data (computer automatically

updates the blowdown flows).Option#2-use manually entered S/G blowdown flow rates.Computer point[F2261A]is more accurate than flow indicators

located in the fan rooms.If the computer point is inoperable

and blowdown flows from the FIS's are used in the calculation

of U1118, then expect U1118 to indicate a different value and adjustment

of NIS may be required.[1]ENSURE S/G blowdown flows are updated by performing

the following on les:[a][b]SELECT"NSSS AND BOP".SELECT"CALORIMETRIC

FUNCTION MENU" D D[c]SELECT"UP-DATE OPERATOR ENTERED SLOWDOWN FLOW'on menu AND PERFORM one of the following options (N/A option not used): 1.IF using computer point[F2261A]S/G Total Slowdown Flow, THEN[a]VERIFY point value is updating (changing values).[b]IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WOo D D D

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Page 24 of 33 Unit---Date---NOTE APPENDIXC Page 2 of 3 Local readings of steam generator blowdown flow are obtained from Panel L-357.2.IF manually updating blowdown flows, THEN[a]RECORD local readings for S/G blowdown flow: Res BLOWDOWN FLOW LOOP (GPM)1 FI-1-152 2 FI-1-156 3 FI-1-160 4 FI-1-164[b]ENSURE blowdown flows above entered in ICS.[c]IF blowdown flows were updated, THEN WAIT a minimum of 10 minutes to allow program to accurately

reflect new value.D

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Page 25 of 33 Unit---Date---NOTE APPENDIXC Page 3 of 3 ICS-printout may be used to document power level and NIS values.Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used)and the printed sheet value (if used).SI acceptance

is satisfied in the body of the instruction.

[2]SELECT"DISPLAY CURRENT CALORIMETRIC

DATA" on ICS Calorimetric

menu AND D PERFORM one of the following:

[a]RECORD the following:

Venturi Core Thermal Power (U1118)Mwt Percent Rated Core Thermal Power (U1127)0/0 OR[b]PRINT power level and NIS values AND ATTACH report to this instruction.

D[3]IF any value isa blue"NCAl" quality, THEN PERFORM the following:

[a]IF cause of bad data is unknown, THEN REQUEST assistance

from MIG or ICS computer engineer.D[b]INITIATE WO if required.D[c]GO TO Appendix D.D

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Page 26 of 33 Unit---Date---NOTE 1 NOTE 2 APPENDIX D Page 1 of 7 CALCULATION

OF CORE THERMAL POWER LEVEL W.ITH INOPERABLE

PLANT COMPUTER (RCST Greater Than 400/0)This appendix provides guidance determining

calorimetric

power when ICS core thermal power indication (U 1118 and U2118)is unavailable

with power above 40%and the computer cannot be restored in time to complete SR 4.3.1.1.1.

0-PI-SXX-000-022.2

requires several hours from initiation

until completion

of power calculation.

[1]IF O-PI-SXX-000-022.2

will be used for calorimetric

data, THEN PERFORM the following:

[a]NOTIFY Systems Engineering

to perform manual calorimetric

calculation

using

[b]MARK remaining steps"N/A" in this appendix.D D

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Page 27 of33 Unit---Date---NOTE 1 NOTE 2 APPENDIX D Page 2 of 7 The remaining steps determine core thermal power by manually entering calorimetric

data on opposite unit's ICS computer.This method requires adding 3.5%to the calculated

power level for additional

conservatism

due to greater errors associated

with indicator error and readability.

Therefore, power level should be reduced to less than or equal to 96.5%before performance.

Calorimetric

calculation

on opposite unit's ICS assumes that blowdown flow is identical on each unit.This error is accounted for in the 3.50/0 correction

factor.[2]IF opposite unit's ICS will be used to perform a calorimetric

calibration, THEN PERFORM the following:

[a]ENSURE reactor power less than or equal to 96.5%.[b]ENSURE reactor power and RCS temperature

stable.D D

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Page 28 of 33 Unit---Date---NOTE 1 NOTE 2 APPENDIX D Page 3 of 7 If ICSis unavailable, Feed flow and feed temperature

may still be available onLEFM panel[LOCL-500-R183]

in Aux Inst Rm.MFW header temp must be greater than 250°F for reliable LEFM data.[3]IFLEFM feed flow and feed temperature

is available on local LEFM panel, THEN PERFORM the following:

[a]RECORD the following data: Paramete*r

Indication

Reading Loop 1 Feedwater Pressure PI-3-37[M-3]psig Loop 2 Feedwater Pressure

[M-3]psig Lo.op 3 Feedwater Pressure PI-3-92[M-3]psig Loop 4 Feedwater Pressure PI-3-105[M-3]psig Loop 1 S/G Pressure PI-1-2A or 28[M-4]psig Loop 2 S/G Pressure I PI-1-9Aor 9B[M-4]psig Loop 3 S/G Pressure PI-1-20A or 20B[M-4]psig Loop 4 S/GPressure

PI-1-27Aor

278[M-4]psig Total Feedwater Flow LEFM Ibm/hr Feedwater Temperature

LEFM of (must be>250°F)IV[b]SELECT Calorimetric

Main Menu screen on other unit's ICS computer.(step continued on next page)D

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Page 29 of 33 Unit APPENDIX D Date Page 4 of 7[3](Continued)

[c]SELECT LEFMSpecial

Offline Calorimetric

on Calorimetric

Menu.[d]ENTER data in ICS from table in substep 3[a].[e]SELECT function key F3 to execute calculation.

[f]PRINT calorimetric

results.[g]VERIFY data was correctly entered in ICS from table in substep 3[a].[h]RECORD Total S/G Thermal Power from calorimetric

printout: MWt----[i]CALCULATE percent power corresponding

to item[h]IV D D D____MWt==34.55 0/0---NOTE The following step adds 3.5%to calorimetric

power to compensate

for additional

errors in this method.The corrected power value below should be used in Section 6.1.U]CAL*CULATE

corrected core thermal power: (substep[i])%+3.5°lb==[k]VERIFY substeps[g]through U].0/0------IV

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Page 30 of 33 Unit APPENDIX D Date Page 5 of 7 NOTE 1 ,2-PI-ICC-003-036.0

provides details on required test equipment for feedwater temperature

measurement.*

[4]IF LEFM feed flow and feed temperature

is NOT available, THEN PERFORM the fol"lowing:

[a]NOTIFY MIG or Systems Engineering

to install precision temperature

monitoring

'equipment

in feedwater header temperature

wells TW-3-197 an.d TW-3-198[TB el.685].[b]RECORD average feedwater header temperature:

of-----(step continued on next page)D MIG or Eng IV

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Page 31 of 33 Unit APPENDIX D Date Page 6 of 7[4](Continued)

[c]RECORD the following data: Parameter Indication

Reading Loop 1 Feedwater Press PI-3-37[M-3]psig Loop 2 Feedwater Press PI-3-50[M-3]psig Loop 3 Feedwater Press PI-3-92[M-3]psig Loop 4 Feedwater Press PI-3-105[M-3]psig Loop 1 S/G Pressure PI-1-2A or 2B[M-4]psig Loop 2 S/G Pressure PI-1-9A or 9B[M-4]psig Loop 3 S/G Pressure PI-1-20Aor

20B[M-4]psig Loop 4 S/G Pressure PI-1-27A or*27B[M-4]psig Loop 1 Feedwater Flow FI-3-35A or 35B[M-4]Ibm/hr Loop 2 Feedwater Flow FI-3-48A or 48B[M-4]Ibm/hr Loop 3 Feedwater Flow FI-3-90A or 90B[M-4]Ibm/hr Loop 4 Feedwater Flow FI-3-1 03A or 103B[M-4]Ibm/hr IV[d]SELECT Calorimetric

Main Menu screen on other unit's ICS computer.[e]SELECT Special Offline Calorimetric

on Calorimetric

Menu.(step continued on nextpage)D D

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Page 32 of 33 Unit APPENDIX D Date Page 7 of 7[4](Continued)

[f]ENTER data in ICS"from substeps 4[b]and 4[c].[g]SELECT function key F3 to execute calculation.

[h]PRINT calorimetric

results.[i]VERIFY data from substeps 4[b]and 4[c]was correctly entered in ICS.U]RECORD Total S/G Thermal Power from calorimetric

printout:____MWt[k]CALCULATE percent power corresponding

to item Ul IV o o____MWt==34.55 0/0------NOTE The following step adds 3.5%to calorimetric

power to compensate

for additional

errors in this method.The corrected power value below should be used in Section 6.1.[I]CALCULATE corrected core thermal power: (substep[k])%+3.5%==[m]VERIFY substeps U]through[I].___%IV

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Page 33 of 33 SOURCE NOTES Page 1 of 1 REQUIREMENTS

STATEMENT Ensure calculation

of thermal power is correct before calibrating

excore detectors.

Excore detectors should be calibrated

based on best available power indication.

NIS*power range calibrations

should be performed periodically

following power ascension above 15%power.Careful consideration

and caution should be exercised before adjusting nuclear instrumentation.

Operations

and Engineering

Management

should be notified if larger than normal channel adjustments

are required.0-SI-OPS-092-078.0

will be revised to allow the use of a Plant Computer program to provide an increased frequency of the performan'ce

of thi"s procedure.

SOURCE DOCUMENT INPO SER 89-23 CAQR sao 90052 INPO SER89-09 INPO SOER 90-03 INPO SOER90-03 LER 328/91005 810 910819 844 IMPLEMENTING

STATEMENT C.1 C.2 C.3 C.4 C.5

co

PREPARED/REVISED BY: JPM#46-1 Page 1 of 13 Rev.0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE

MEASURE B.1.g JPM#46-1 SHUTDOWN THE DIESEL GENERATORS

(1A-A&18-8)Date/VALIDATED BY:*APPROVED BY: (Operations

Training Manager)Date/Date/CONCURRED:

    • (Operations

Representative)

Date/*Validation

not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual

step changes that do not affect the flow of the JPM.**Operations

Concurrence

required for new JPMs and changes that affect the flow of the JPM (if not driven by a procedure revision).

JPM#46-1 Page 2 of 13 Rev.0 NUCLEAR TRAINING REVISION/USAGE

LOG REVISION DESCRIPTION

OF V DATE PAGES PREPARED/NUMBER REVISION AFFECTED REVISED BY: 0 Initial Issue ALLv-Specify if the JPM change will require another validation (Y or N).See cover sheet for criteria.

JPM#46-1 Page 3 of 13 Rev.0 SEQUOYAH NUCLEAR PLANT RO/SRO JOB PERFORMANCE

MEASURE Task: Shutdown the Diesel Generators

(1 A-A&18-8)JAiT A task#: 0640060101 (RO)KIA Ratings: 064K1.01 064A2.08 064A3.06 (4..1/4.4)(2.5/2.7)(3.3/3.4)064A1.08 064A2.13

064A4.06 (3.1/3.4)(2.6/2.8)(3.9/3.9)064A2.04 064A3.03 064A4.01 (2.7/3.0)(3.4/3.3)

(4.0/4.3)Task Standard: Diesel Generators

"1 A-A"&"18-8" have been shutdown in accordance

with EA-82-1.Evaluation

Method: Simulator__X__In-Plant--'""--===================================================================================

Performer:

Performance

Rating: SAT Evaluator:

NAME UNSAT SIGNATURE Performance

Time DATE Start Time-,--__Finish Time---==================.=================================================================

COMMENTS

JPM#46-1 Page 4 of 13 Rev.0 SPECIAL INSTRUCTIONS

TO EVALUATOR:

1.Critical steps identified

by an asterisk (*)2.Sequenced steps identified

by an"s" 3.Any UNSAT requires comments 4.Initialize

simulator in IC#191.lf IC-191 not available, reset to IC#5 Trip the reactor, use 1-M-1 handswitchto

emergency start the diesels generators.

Close TDAFW level control valves.5.When directed to perform section 4.2, set BOTH RF EGR11 and EGR12to TEST and THEN BOTH back to NORMAL*to reset the DIG start signal.Set EGR07 and EGR 08 to RESET to reset the 86LOR for the DGs 6.Acknowledge/reset

alarms on all panels.7.This scenario will require a console operator.8.Ensure operator performs the following required actions*for

SELF-CHECKING;

a.Identifies

the correct unit, train, component, etc.b.Reviews the intended action and expected response.c.Compares the actual response to the expected response.Validation

Time: CR.20 mins Local....,....--

Tools/Equipment/Procedures

Needed:

, References:

Reference EA-82-1 Title DIGs in Standb Rev No.2

READ.TO OPERATOR Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for this job performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handoutsheet

I provided you.INITIAL CONDITIONS:

1.The Unit tripped due to an*inadvertent

safety injection.

2.The safety injection has been terminated

and the plant has been stabilized

in MODE 3.3.The Diesel Generators

have been running unloaded for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes.4.The status file is complete and there are no outstanding

configuration

log entries present for the Diesel Generators.

INITIATING

CUES: 1.You are the Unit 1 CRO and have been directed to shutdown the Unit 1 Diesel Generators

per EA-82-1.2.The 1 A-A DIG is to be shutdown first.3.All Shutdown Boards are energized by offsite power and the SI signal has been reset.4.Informthe SM when 1A and1B DIGs have been shutdown per EA-82-1.

Job Performance

Checklist:

STEP/STANDARD

JPM#46-1 Page 5 of 13 Rev.0 SAT/UNSAT STEP 1.: Obtain appropriate

copy of procedure.

SAT STANDARD: Operator obtains a copy of EA-82-1 and procedes to Section 4.1.COMMENTS: UNSAT Start Time__STEP 2.: 1.SELECT DIG to be shut down:*DIG 1A-A__*DIG 18-8__*DIG 2A-A__*DIG 28-B SAT UNSAT STANDARD: Operator checks 1 A-A and 18-B diesel generators

being selected.COMMENTS: STEP 3.: Cue: 2.IF EA-202-1 was NOT used to unload the selected DIG, THEN DISPATCH AUO to perform Section 4.2 to reset selectedD/G

emergency start signal.Role Playas AVO and accept EA-82-1, Section 4.2.Report that you will report to him when complete.SAT UNSAT Critical Step Booth Operator: Set BOTH RF EGR11 and EGR12 to TEST and THEN BOTH back NORMAL to reset the DIG start signal.Then, setEGR07 and EGR 08 to RESET Cue: After performing

the

Role Playas AVO and report EA-82-1, Section 4.2 complete.STANDARD: Operator dispatches

AUO with EA-82-1, section 4.2.COMMENTS: STEP 4.: 3.GO TO appropriate

section based on table below: SAT rF SELECTED DIG THEN GO to SECTION OlG DIGDIGDIG 1 A-A 18--8 2A-A 2B-B ,.J..l"""t}UNSAT

..Unloaded greaterihaR:

2 Purging: DiG Combustibles.

Section Unloaded tess than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,£nutting C\Q"\vn OlG.o o o o o o o o STANDARD: Operator determines

that section 4.3 is the appropriate

section since the DIG has been running unloaded more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.(also checks the 1 A-A and 1 B-B boxes.)COMMENTS:

Job Performance

Checklist:

STEP/ST ANDARD JPM#46-1 Page 60f 13 Rev.0 SAT/UNSAT 1.POSITION selected DIG MODE SELECTOR switch to PARALLEL: The following steps are from section 4.3.NOTE: STEP 5.: DiG'lB-B 28-8 MODE SElECTOR S'wrrCH HS...S2-1'g H3-B2-7a H5-82-1o:08

PARAlLEL*4

D'SAT UNSAT Criti'cal Step STANDARD: Operator places O-HS-82-18, DG 1 A-A MODE SELECTOR, to PARALLEL.COMMENTS: STEP 6.: 2.TURN selected DIG SYNCHRONIZE

switch to SYN: SAT rUG 1A,-A 18-9 2A-A 28-9 SYNCHRONiZE

SWITCH 1-HS--57-47 1-HS-57-14

.2-HS--57-47

2-HS-57-14

t.J UNSAT Critical Step STANDARD: Operator places O-HS-57-47

DG 1 A-A SYNCHRONIZE, to SYN.COMMENTS: STEP 7.: 3.ENSURE selected DIG VOLTAGE REGULATOR switch*inAUTO: SAT DiG 1 A.-A 2A-A.28-B VOLTAGE REGULATOR S'WITCH:H S-8:2-4 2: H

HS-S2:-1:Q.2

PUlL-P-AUTOD: o UNSAT STANDARD: Operator verifies O-HS-82-12, DG 1 A-A VOLTAGE REGULATOR to PULL-P-AUTO.

COMMENTS:

Job Performance

Checklist:

STEP/STAN DARD JPM#46-1 Page 7 of 13 Rev.0 SAT/UNSAT STEP 8.: 4.ADJUST running voltage to match incoming voltage USING DIG VOLTAGE REGULATOR switch: SAT DlG IN:=eOMI1NG

VOLTAGE El-82-e4, El-82-M RUNN:IN:G'VOLTAGE E1-82-5 EI-82-35 EI-82-95;VOL T.AGE M ATC HE 0 4 o UNSAT Critical Step STANDARD: Operator adjusts 0-HS-82-:12, DG 1A-A VOLTAGE REGULATOR, to match voltages on O-EI-82.,.4

and O-EI-82-5.

COMMENTS: STEP 9.: 5.ADJUST selected DIG SPEED CONTROL switch UNTIL associated

synchroscope

rotating slowly in FAST direction:

SAT DlG 18-8:2.A-A 28-8 SPEED CONTROL S)'NCHROSCOPE

SLOV4'lY[IN FAST ,SWITCH

HS-82..*13;<;1-82-1 0;HS-82-43 X!-82-,31 0 UNSAT Critical Step STANDARD: Operator adjust 0-HS-82-13

until synchroscope

O-XI-82-1 is rotating slowly in the fast direction.

COMMENTS: STEP 10.: 6.WHEN synchroscope

needle is at 12 o'clock" position, THEN CLOSE selected DIG output breaker: SAT 016 2A-A 28-B XJ-82-31

DiG OUTPUT BREA;KER'l-H8-57-46A'1-HS-51-'73A

2-HS-57-46A 2-HS-57-73,A.CLOSED*i o o 0, UNSAT Critical Step STANDARD: Operator places 1-HS-57-46A

to the close position when synchroscope

O-XI-82-1is

at the 12 O'clock position resulting in the closing of the DG electrical

breaker as indicated by Red Light LITabovethe breaker handswitch.

COMMENTS:

Job Performance

Checklist:

JPM#46-1 Page 8 of 13 Rev.0 (STEP 11.: STEP/ST ANDARD 7.ADJUST selected DIG SPEED CONTROL switch to raise DIG MW load to 1.6 MW: SAT/U N SAT SAT DIG UNSAT LA-.A.28-8

  • 3 HS-8-2-43 HS-a2-7:3 Eli-92**'1

OA El-B-2-'1:DOA, o o o o Critical Step ST AND.ARD: Operator intermittently

places O-HS-82-13

to RAISE until the MW loading on O-EI-82-1 OAincreases

to 1.6 mw.COMMENTS: STEP 12.: 8.MAINTAIN+1 MVAR (OUT)for selected DIG, WHILE paralleled

with offsite power: DlG VOLTAGE:D/G REGULATOR

iDlG M:EG.A.VARS

+1 MVAR'1.'SAT UNSAT lA-A 18-8 2B-8 HS-82-12 HS-8242 HS-82-I2£:1-82-1 D'l A o o o o Critical Step STANDARD: Operator places O-HS-82-12

to RAISE to establish the MVAR loading on O-EI-82-11A

to+1 MVAR outgoing, then maintains this MVAR loading as the DG is loaded'by intermittently

placing O-HS-82-12

to RAISE.COMMENTS: STEP 13.: Cue: 9.DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG.Role Playas AUO acknowledge

the direction to monitor theD/G 1A-A exhaust stack.SAT UNSAT STANDARD: Operator dispatches

an AUO to the DIG building to monitor DIG 1A-A exhaust.COMMENTS:

Job Performance

Checklist:

STEP/ST ANDARDJPM#46-1 Page 9 of 13 Rev.0 SAT/UNSAT STEP 14.: 10.LOAD selected DIG to 4.0 MW USING its DIG SPEED CONTROL switch WHILE observing the following guidelines:

a.IF stack exhaust smoke becomes twice as dense as normal during loading, THEN STOP DIG loading UNTIL condition clears.b.WHEN exhaust smoke returns to normal, THEN CONTINUE DIG loading.c.DO NOT CONTINUE this procedure UNTIL the following conditions

are met:*DIG load at 4.0 MW AND*Stack exhaust NORMAL.SAT UNSAT Critical Step Cue: When the AUO is asked,*state

the exhaust has cleared up and now appears normal.STANDARD: Operator loads the DIG 1 A-A to 4.0 MW by intermittently

placing82-13 to RAISE until theMW loading on 0-EI-82-10A

increases to 4.0 mw.COMMENTS: STEP 15.: 11.ADJUST selected DIG SPEED CONTROL switch to lower DIG MW load to 0.5 MW: SAT DiG SPEEDCO:NTROL

HS-d2-'13 HS-:E2-43 H5-32-73 o o o UNSAT Crit.ical Step STANDARD: Operator places O-HS-82-13

to LOWER until the MWloading on 0-EI-82-10A

reduces to 0.5 mw.COMMENTS: STEP 16.: 12.ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero: SAT;016 DIG VOLTAGE.Qj'-G MEGAVARS 0VAR,!REGULATOR SWITC.H UNSAT lA-A 2A-A 2B-8 H5-82-12 HS-82-42 HS-82-72 HS-S2-1G2

1 A o o D o Critical Step STANDARD: Operator places O-HS-82-12

to LOWER until the MVAR loading on 0-EI-82-11A

reduces to o.COMMENTS:

Job Performance

Checklist:

STEP/STAN DARD JPM#46-1 Page 10 of 13 Rev.0 SAT/UNSAT STEP 17.: 13.PLACE selected DIG output breaker control switch to TRIP: SAT DiG*1B,.;6.2A-A[hfG

1-iHS-57-46.A.

'1

-13A.2-H3-51-46.A.

2**H3-0:1-13.A.o o o o UNSAT Critical Step STANDARD: Operator places 1-HS-57-46A to the TRIP position.COMMENTS: STEP 18.: 14.GO TO Section 4.4 to shut down DIG.SAT STANDARD: Operator goes to section 4.4 to shut down the DIG 1 A-A.COMMENTS: Evaluator Note: The following steps are from Section 4.4 UNSAT STEP 19.:1.VERIFY selected DIG unloaded with output breaker open: SAT DIG 18-8 2A-A 28-8 DlGOUTPUT BREAKER BREA.KER HAN D SWITCH 1@22 2-HS..*54-45A UNLOADED 8.OUTPUT BREAKER OPEf4D o o o UNSAT STANDARD: Operator verifies DIG 1 A-a output breaker open by green light LIT over Handswitch

1-HS-54-46A.

C'OMMENT'S:

STEP 20.: 2.PLACE selected D/G(s)CONTROL START-STOP

switch to STOP: SAT DiG 18-9 28-8 DIG CO:NTROl START-S*TOP

o o u u UNSAT Critical Step NOTE: Operator may elect to turn the synchroscope

on to verify D/G goes to idle speed when HS is placed to stop.ST*ANDARD:

Operator places handswitch on panel 0-M-26, to the STOP.COMMENTS:

Job Performance

Checklist:

STEP/STANDARD

JPM#46-1 Page 11 of 13 Rev.0 SAT/UNSAT STEP 21.: 3.WHEN selectedD/G(s)

has run at idle speed (400 rpm)for 10 minutes, THEN VERIFY DIG shuts down and speed drops to zero: SAT UNSAT DiG:lA,-A NOTE: Cue: u o 2B-iB Override AN:OVRDN[905]

to OFF to clear the 40 RPM running alarm.When alarm clears, CUE: 10 minutes have elapsed If A-Va notified, play role and state: DIG is now at zero speed.STANDARD: Operator addresses need to monitor this step.They may contact the AUO to have himlher contact the UO when speed is zero.COMMENTS: STEP 22.: 4.ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position: SAT UNSAT OiG:1

lB-B; 1-H*S-B2:-

1,8:1--HS-82-4:B

o o STANDARD: Operator places handswitch

1-HS-82-18, on

0-M-26, to be in PUSH TO UNIT position.COMMENTS: STEP 23.: 5.ENSURE selected DIG SYNCHRONIZE

switch is in OFF: SAT DlG*2A-A:1-H*S-57-14

2-H*S-57-47

2-HS-57-74

u o o o UN"SAT STANDARD: Operator places handswitch

1-HS-57-47, on panel 0-M-26, in the OFF position.COMMENTS:

J0b Performance

Checklist:

STEP/STANDARD

JPM#46-1 Page 12 of 13 Rev.0 SAT/UNSAT STEP 24.: 6.WHEN selected D/G(s)have cooled, THEN ENSURE ERCW valves to DIG heat exchangers

closed: SAT UNSAT:O/G Critical Step tA.--A LH-B

1-HS.-<67--e=;eA.

1-

2-H,S-=B7--67

A.2-HS-67-e5.A.:0 o=0:0:0 o Cue: Play role of AUO: I will monitor DIG temperature

and ensure DG 1A-A ERCW valves are closed when DIG reaches ambient temp.STANDARD: Operator addresses need to monitor this step.They may contact the AUO to have himlher monitor DIG temperatures

and shut the ERCW valve,1-FCV-67-66, when the DIG is at ambient conditions.-COMMENTS:

STEP 25.: 7.GO TO Section 4.1, step in effect.SAT STANDARD: Operator returns to section 4.1 and determines

the other DG needs to be shutdown.UNSAT Cue: COMMENTS: When candidate returns to section 4.1 to shutdown the*other Diesel Generator, state"We'll stop here." End of JPM Stop Time__

Directions

to Trainee: I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM.I will provide initiating

cues and reports on other actions when directed by you.When you complete the task successfully, the objective for thisjob performance

measure will be satisfied.

Ensure you indicate to me when you understand

your assigned task.To indicate that you have completed your assigned task return the handout sheet I provided you.INITIAL CONDITIONS:

1.The Unit tripped due to an inadvertent

safety injection.

2.The safety injection has been terminated

and the plant has been stabilized

in MODE 3.3.The Diesel Generators

have been running unloaded for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes.4.The status file is complete and there are no outstanding

configuration

log entries present for the Diesel Generators.

INITIATING

CUES: 1.You are the Unit 1 eRa and have been directed to shutdown the Unit 1 Diesel Generators

per EA-82-1.2.The 1 A-A DIG is to be shutdown first.3.All Shutdown Boards are energized by offsite power and the SI signal has been reset.4.Inform the SM when 1A and1B D/Gshave been shutdown per EA-82-1.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-82-1 PLACING DIGs IN STANDBY Revision 2-QUALITY RELATED Marie-Hankins PREPARED/PROOFREAD

BY:-

RESPONSIBLE

ORGANIZATION:

OPERATIONS

APPROVED BY:

_EFFECTIVE DAT-E: 26 May 03 REVISION DESCRIPTION:

Revised section 4.4 to add steps to place the Mode Selector switch in PUSH IN UNIT position and turn the Sync Switch to OFF.This is an intent change.Added HS UNID for D/G output breakers in section 4.4 step 1.Added a note in section 4.1 to clarify DIG's have not been returned to TS operability

but are place-d ina condition for Auto Restart, if required prior to exiting the EOP's.This is a non-intent

change.

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 page 2 of 16 1.0 PURPOSE To shut down unloaded DIGs and place the DIGs in a standby condition.

If a DIG has been running unloaded greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, thisEAP will load it to purge combustibles

and then unload it and shut it down.2.0 SYMPTOMS AND ENTRY CONDITIONS

2.1 Entry Conditions

A.E-O, Reactor Trip or Safety Injection.

B.E-1, Loss of Reactor or Secondary Coolant.C.E-3, Steam Generator Tube Rupture.D.ECA-2.1, Uncontrolled

Depressurization

of All Steam Generators.

E.ECA-3.1, SGTR and LOCA-Subcooled Recovery.F.ECA-3.2, SGTR and LOCA-Saturated Recovery.G.ECA-3.3, SGTR Without Pressurizer

Pressure Control.H.ES-1.1, 81 Termination.

I.ES-1.2, Post LOCA Cooldown and Depressurization.

3.0 PRECAUTIONS

AND LIMITATIONS

3.1 Precautions

A.If the accountability

siren sounds, the operator should continue performing

this procedure.

The SOS will remain aware of procedure progress and location of performing

personnel.

3.2 Limitations

A.This EAP does NOT meet all procedural

and Technical Specification

requirements

for returning the DIGs to a full standby condition.

This procedure only returns the DIGs to a condition for auto-re*start

to ensure availability

if needed prior to exiting the EOPs.

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 3 of 16 4.0 OPERATOR ACTIONS 4.1 Section Applicability

1.SELECT DIG to be shut down:*DIG 1A-A*DIG 1 B-B*DIG 2A-A*D/G28-8__NOTE If EA-202-1 was used to unload the selected DIG, then the DIG emergency start signal and the shutdown board blackout relays have already been reset.2.IF EA-202-1 was NOT used to unload the selected DIG, THEN DISPATCH AUO to perform Section 4.2 to reset selected DIG emergency start signal.3.GO TO appropriate

section-based on table below: D THEN DIG DIG DIG DIG IF SE-LECTED DIG GO TO SECTION 1A-A 1B-B 2A-A 28-8Unloaded greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Section 4.3,DDDD Purging DIG Combustibles.

Unloaded less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Section 4.4,DD D D Shutting Down DIG.

SQN EA-82-1 PLACING DIGs IN*STANDBY Rev.2 1,2 Page 4.of 16 4.1 Section Applicability (Continued)

4.IF another DIG to be shut down, THEN GO TO Step 4.1.1 D NOTE This procedure places the DIG's in a condition for Auto-Restart, if required prior to exiting the EOP's.Restoration

to T8 operability

and procedural

requirements

for standby alignment is performed after the EOP's are exited.5.RETURN TO procedure and step in effect.END OF SECTION D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 5 of 16 4.2 Resetting DIG Auto Start Signals NOTE Performance

of Steps 4.2.1 and 4.2.2 are required thefirsttime this section is performed but their performance

is not required on subsequent

passes through this section.1.NOTIFY UO to verify SI reset.2.RESET DIG emergency start signals by performing

the following:

[6.9 KV shutdown board room]a.PLACE all DIG[43T(Ll]switches to TEST: SHUTDOWN BOARD LOGIC SWITCH TEST PANEL1 A-A 43T(L)D 18-8 43T(L)D 2A-A 43T(L)D 28-8 43T(L)D b.VERIFY emergency start signals RESET by observing amber lights lit SHUTDOWN BOARD LOGIC PANEL AMBER LIGHT LIT1 A-A D 18-8 D 2A-A 0 28-8 D D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 6 of 16 4.2 Resetting DIG Auto Start Signals (Continued)

C.PLACE 8.11 DIG[43T(L)]switches to NOR: SHUTDOWN BOARD LOGIC PANEL SWITCH NOR1 A-A 43T(L)D 18-8

D 2A-A 43T(L)D 28-8 43T(L)D 3.PERFORM the following:

a.VERIFY DIG[86 LOR]red lights DARK: DIG RELA Y BOARD RED LIGHT DARK1 A-A D 18-8 D 2A-A D 28-8 D b.PLACE selected DIG[86 LOR]switch to RESET: DIG RELAY BOARD SWITCH RESET1 A-A 86 LOR D 18-8 86 LOR D 2A-A 86 LOR D 28-8 86 LOR D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 7 of 16 4.2 Resetting DIG Auto Start Signals (Continued)

4.GOTO Section 4.1, step in effect.END OF SECTION D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1;2 Page 8 of 16 4.3 Purging DIG Combustibles

CAUTION NOTE Only one diesel shall be operated in parallel with off-site power at any time.This section purges the DIG of any combustibles

accumulated

during the unloaded condition prior to shutting down the DIG.1.POSITION selected DIG MODE SELECTOR switch to PARALLEL: DIG MODE SELECTOR SWITCH PARALLEL1 A-A HS-82-18 D 18-8 HS-82-48 D 2A-A HS-82-78 D 28-8 HS-82-108 D 2.TURN selected DIG SYNCHRON1ZE

switch toSYN: DIG SYNCHRONIZE

SWITCH1 A-A 1-HS-57-47

D 18-8 1-HS-57-74

D 2"A-A 2-HS-57-47

D 2"8-8 2-HS-57-74

D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 9 of 16 4.3 Purging DIG Combustibles (Continued)

3.ENSURE selected DIG VOLTAGE REGULATOR switch in PULL-P-AUTO:

DIG VOLTAGE REGULATOR PULL-P-AUTOSWITCH 1 A-A HS-82-12 D 18-8 HS-82-42 D 2A-A

D 28-8 HS-82-102 D 4.ADJUST running voltage to match incoming voltage USING DIG VOLTAGE REGULATOR switch: DIG INCOMING RUNNING VOL TAGE MATCHEDVOLTAGE VOLTAGE 1 A-A

EI-82-5 D 18-8 EI-82-34 EI-82-35 D 2A-A EI-82-64 EI-82-65 D 2"8-8 EI-82-94" EI-82-95 D 5.ADJUST selected DIG SPEED CONTROL switch UNTIL associated

synchroscope

rotating slowly in FAST direction:

DIG SPEED CONTROL SYNCHROSCOPE

SLOWLY IN FAST SWITCH DIRECTION1 A-A HS-82-13 XI-82-1 D 18-8 HS-82-43 XI-82-31 D 2A-A HS-82-73 XI-82-61 D 28-8 HS-82-103 X"I-82-91 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 10 of 16 4.3 Purging DIG Combustibles (Continued)

NOTE When closing the DIG output breaker at 12 o'clock position, consideration

should be given to speed of rotation of synchroscope

needle and time it takes to close the breaker.6.WHEN synchroscope

needle is at 12 o'clock" position, THEN CLOSE selected DIG output breaker: DIG SYNCHROSCOPE

DIG OUTPUT CLOSEDBREAKER 1 A-A XI-82-1 1-HS-57-46A D 18-8 XI-82-31 1-HS-57-73A D 2A-A XI-82-61 2-HS-57 D 28...8 XI-82-91 2-HS-57-73A

D 7.ADJUST selected DIG SPEED.CONTROL

switch to raise DIG MW load to 1.6 MW: SPEED CONTROL 1.6 MWDIG SWITCH DIG MEGAWATTS 1 A-A HS-82-13 EI-82-10A D 18-8 HS-82-43 EI-82-40A D 2A-A HS-82-73 EI-82-70A D 28-8 HS-82-103 EI-82-100A

D 8.MAINTAIN+1 MVAR (OUT)for selected D/G,WHILE paralleled

with offsite power: DIG VOLTAGE+1 MVAR" DIG REGULATOR SWITCH DIG MEGAVARS 1 A-A HS-82-12 EI-82-11A D 18-8 HS-82-42

D 2A-A HS-82-72 EI-82-71A D 28-8 HS-82-102 EI-82-101A

D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 11 of 16 4.3 Purging DIG Combustibles (Continued)

9.DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG.D 10.LOAD selected DIG to 4.0 MW USING its DIG SPEED CONTROL switch WHILE observing the following guidelines:

a.IF stack exhaust smoke becomes twice as dense as normal during loading, THEN STOP DIG loading UNTIL condition clears.b.WHENexhaustsmoke

returns to normal, THEN CONTINUE DIG loading.C.DO NOT CONTINUE this procedure UNTIL the following conditions

are met:*DIG load at 4.0 MW AND*Stack exhaust NORMAL.11.ADJUST selected DIG SPEED CONTROL switch to lower DIG MW load to 0.5 MW: DIG SPEED CONTROL SWITCH 0.5 MW1 A-A HS-82-13 D 18-8 HS-82-43 D 2A-A HS-82-73 D 28-8 HS-82-103 D D D D D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 12 of 16 4.3 Purging DIG Combustibles (Continued)

12.ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero: DIG DIG VOLTAGE DIG MEGAVARS o MVAR" REGULATOR SWITCH 1A-A HS-82-12 EI-82-11A D 18-8 HS-82-42 EI-82-41A D 2A-A HS-82-72 EI-82-71A D 28-8 HS-82-102

01A D 13.PLACE selected DIG output breaker control switch to TRIP: DIG DIG OUTPUT BREAKER TRIPPED" 1 A-A 1-HS-57-46A D 18-8 1-HS-57-73A D 2A-A 2-HS-57-46A D 28-8 2-HS-57-73A

D 14.GOTO Section 4.4 to shut down DIG.END OF SECTION D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 13 of 16 4.4 Shutting Down DIG 1.VERIFY selected DIG unloaded with output breaker open: DIG DIG OUTPUT BREAKER UNLOADED&OUTPUT BREAKER HANDSWITCH

BREAKER OPEN1 A-A 1912 1-HS-54-46A

D 18-8 1914 1-HS-57-73A

D 2A-A 1922 2-HS-54-46A

D 28-8 1924 2-HS-57-73A

D 2.PLACE selected D/G(s)CONTROL START-STOP

switch to STOP: DIG DIG CONTROL STOP-V START-STOP SWITCH 1 A-A HS-82-14 D 18-8 HS-82-44 D 2A-A HS-82-74 D 28-8 HS-82-104 D 3.WHEN selected D/G(s)has run at idle speed (400 rpm)for 10 minutes, THEN VERIFY DIG shuts down and speed drops to zero: DIG ZERO RPM-v D 18-8 D 2A-A D 28-8 D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 14 of 16 4.4 Shutting Down DIG (Continued)

4.ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position: DIG MODE SELECTOR SWITCH PUSH IN UNIT1 A-A 1-HS-82-18

D 18-8 1-HS-82-48

D 2A-A 2-HS-82-78

D 28-8 2-HS-82-108

D 5".ENSURE selected DIG SYNCHRONIZE

switch is in OFF: DIG SYNCHRONIZE

SWITCH OFF1 A-A 1-HS-57-47

D 18-8 1-HS-57-74

D 2A-A 2-HS-57-47

D 2B-8 2-HS-57-74

D

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 15 of 16 4.4 Shutting Down DIG (Continued)

6.WHEN selected O/G(s)have cooled, THEN ENSURE ERCW valves to DIG heat exchangers

closed: DIG ERCW TO DIG HEAT EXCHANGERS

CLOSED1 A-A 1-HS-67-66A D 1-HS-67-68A D 1-HS-67-67 A D 1-HS-67-65A D 2A-A 2-HS-67-66A D 2-HS-67-68A D 2B-B 2-HS-67-67 A D 2-HS-67-65A D 7.GO TO Section 4.1, step in effect.END OF TEXT-0

SQN EA-82-1 PLACING DIGs IN STANDBY Rev.2 1,2 Page 16 of 16 5.0 REFERENCES

None.

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