ML071550459
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| ML071550459 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/09/2007 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-327/07-301, 50-328/07-301 | |
| Download: ML071550459 (134) | |
See also: IR 05000327/2007301
Text
{{#Wiki_filter:Final Submittal
(Blue Paper)
SEQUOYAH APRIL/MAY 2007 EXAM
EXAM NOS. 05000327/2007301
AND 05000328/2007301
APRIL 9 - 11, 2007 AND
MAY 9, 2007 (written)
1. Administrative JPMs 2. In-plant JPMs 3. Control Room JPMs (simulator JPMs)
JPM 8 .1 .a
Page 1 of 10
Rev 0
SEQUOYAH NUCLEARPLANT
JOB PERFORM ANCE MEASURE
B.1.a
Raise Power to 10-3 %
(
Original Signatures on File
PREPARED!
REVISED BY: Date!
VALIDATED BY: * Date!
APPROVED BY: Date!
(Operations Training Manager)
CONCURRED: ** Date!
(Operations Representative)
* Validation not required fo r minor enha nceme nts, procedure Rev changes that
do not affec t the JP M, or individual step changes that do not affect the flow of
the J PM.
** 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.a
Page 2 of 10
RevO
/
NUCLEAR TRAINING
REVISION/USAGE LOG
Revision Desc rip tion Pages Prepared/
Number Of Revis ion V Date Affected Revised Bv:
0 Initial issue Y 3/08/07 Ali RH Evans
I
( i
I
I
v - Specify if the JPM change will require another validation (Y or N).
See cover sheet for criteria.
JPM B.1.a
Page 3 of 10
Rev 0
SEQUOYAH NUCLEAR PLANT
RO/SRO
( JOB PERFORMANCE MEASURE
Task:
Raise Reactor Power to 10.3%
JAITA task # :
0010190101, Operate the Control Rod Drive System to bring the reactor critical
0010100101, Manually open the Reactor Trip Breaker from the Controi Room
3110140601, Respond to Continuous Rod Withdrawal per AOP-C.01
KiA Ratings:
192008 K1.08 3.5/3.6
001K5.18 4.2/4.3
001A3.08 3.9/4.0
001AK1.01 3.4'/3.7
001AA2.05 4.4/4.6
Task Standard :
Reactor is tripped in response to uncontrolled rod withdrawal.
Evaluation Method: x
Simulator _--!O-_~ In-Plant _
===================================================================================
Performer:
( NAME Start Time
Performance Rating: SAT UNSAT Performance Time Finish Time
Evaluator: /
SIGNATURE DATE
===================================================================================
COMMENTS
JPM B.1.a
Page 4 of 10
Rev 0
SPECIAL INSTR UCTIONS TO EVALUATOR:
1. Sequenced steps identified by an "s"
2. Any UNSAT requires comments
3. Ensure operator performs the following required actions for SELF-CHECKING;
a. Identifies the correct unit, train, component, etc.
b. Reviews the intended action and expected response.
c. Compares the actual response to the expected response.
4. Initialize simulator to IC-91
5. Ensure Audio-Count Rate Multiplier is set on the 'xt ' scale
6. Acknowledge any associated alarms.
Initialize Simulator to IC-91
Val idation Time: CR. 21 mins Loca l
To ol S/Equ ipment/Procedures Needed:
0-GO-2 Mark Up, 0-SO-B5-1 Mark Up, Counts Doubling table, 11M Plot
Referenc es'
Reference Title Rev No.
A. 0-GO-2 Unit Startup from Hot Standbv to Reactor Critical 26
B. 0-50*85*1 Control Rod Drive Svstem 32
C. AOP-C.O l Rod Control System Malfunction 16
= = == = = == == = = = = = = = ~ = = = = = == = = == ==== = = = = = === = = = = === === == = = = = = = = = = = = = = = = = = = = = = = = =
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 initialing 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:
A rea ct or startup is in progress in accordance with 0-GO-2 , Reactor Startup. T he following
conditions exist:
* All shutdown bank rods a re fully withdrawn .
* Co nt rol Bank "0 " is at 127 ste ps .
* T he estimated critical pos ition is 155 steps on Co ntrol Bank "0".
* Most rece nt 11M predicts 150 steps o n Cont rol Bank 0
* You are at the e" doubling of source range cou nts .
* All pre cautions , lim itations , prerequisites and preceding steps for performance of the
task have been met or successfully performed .
INITIATING CUES:
The U nit Supervisor directs you to continue with the reactor startup and withdraw control
rods to criticality and increase power to take critical data in accordance with 0-GO-2,
Unit Startup from Hot Standby to Reactor Critical, section 5 .2, beginning at Step 55, and
0- SO-85-1 sectio n 6.3, step 41 .
You are to notify th e Unit Supervisor whe n critical data has been taken.
JPM B.1 .a
Page 5 of 10
RevO
Job Performance Checklist:
STEP/STANDARD SATIUNSAT
( STEP 1.: [55] If ICRR plot trend indicates acceptable ECC, Then initiate rod withdrawal _SAT
using SO-85-1 to seventh doubling range (App. C) or criticality.
_ UNSAT
STANDARD: Candidate determines that 7 doubling is approximately 2400 CPS on
each SR channel. Determines that ICRR indicates acceptable ECC (+/-
1000 pcm of estimated). Initiates rod withdrawal by placing IN-HOLD*
OUT switch1 -HS-85-5111 to the OUT position.
Start Time_ _
NOTE: Refer to jpm step 3 for critical step on determining reactor is critical. Critical Step
COMM ENT S:
Procedure note prior to step 56:
Steps 5.3(56) th rough 5.3(58) may be repeated as necessary if rod motion is stopped
prior to reaching doubling range or criticality.
STEP 2. [56] Whe n any of the following conditions are met: _ SAT
* SR count rate reaches or exceeds seventh doubling range _ UNSAT
determined in Appendix C or
( * Bank 0 rods reach fully withdrawn position or
* Operators or Reactor Engineer determine that rod motion should
be stopped
THEN STOP outward rod motion
STANDARD : This step will NOT be applicable at this time
COMMENTS:
Note : Candidate may stop rod withdrawal when P*6 is received.
When P*6 is received, action will be taken per procedure step 62 of
D-GO*2
-------- - ._- -_. - _._--
JPM B.1.a
Page 6 of 10
RevO
Job Performance Checklist :
STEP/STANDARD SATIU NSAT
(
STEP 3. [57] If Reactor is critical, then go to step 5.2(59) (NA Step 5.2(58). - SAT
STANDARD: Perf ormer determ ines the reacto r is cr itic al by obse rv ing a stable - UNSAT
startup rat e with no addition of positive reac tiv ity prio r to rea ching
10--3%power and procedure step 58 will be NA.
Cue: If necessary, ask operator If the reactor Is critical. Cr itical Step
NOTE: If applicant states that the reactor Is NOT critical , t his is co nsidered UNSAT
performance.
CO MMENTS:
STEP 4. [59] If any of the following conditions exist: - SAT
* Criticai conditions cannot be achieved within the +/- 750 pcm - UNSAT
termination band or
* Critical cond itions cannot be achieved within the +/- 1000 pcm
- allowable limit s or,
* Critical conditions can not be achieved above rod insert ion limit or
* Reactor startup must be aborted for other reasons,
( Then perfo rm the fo llowing to abort reactor startup:
* STOP rod withdrawa l
* INITIATE insertion of control banks
* PERFORM Appendi x D, Actions if reactor startup must be aborted
* DO NOT cont inue this section
STA NDARD : Cand idate determines this step does NOT apply
CO MMENTS:
STEP 5. [6 0] If reactor is subcritical with rods at fully withdrawn position, then - SAT
perform Append ix E Actions if reactor subcritical with rods fully
withdrawn. - UNSAT
STANDARD: Candidate determ ines that this step is NA
COMMENTS:
JPM B.1.a
Page 7 of 10
Rev 0
Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
( STEP 6. [61] If the reactor is critical with SUR less than 0.3 DPM, and SAT
4 -
Intermediate Range NIS <P-6 (1E* %), then perform the following:
- UNSAT
* If Bank D control Rods are BELOW the fully withdrawn position,
then operate control rods to establish a positive SUR of
approximately 0.3 DPM.
STANDARD: Candidate evaluates IR SUR and if necessary, withdraws control
bank D to establish a 0.3 DPM SUR
COMMENTS:
Procedure not es prior to step 62:
1. Blo cki ng t he SRM tr ip wi th HS*92-5001 and HS-92-5002 will disable the detector
outputs and rem ove t he audio count rate signa l
2. Step 5.3(62) may be performed at time of criti cality , if re~u ired, Sourc e Range
reactor trip must be BLOCKED before trip set po int of 10 CPS
-
STEP 7. [62] When annunciator window XA-55*4A, window D-2 is iit, then - SAT
( * Record both Source Range readings - UNSAT
* Record both Intermediate Range readings
4
* Verify a minimum of 1 IRM channel greater than or equal to 1F %
RTP.
Crit ical Step
* Block source range reactor trip by momentar ily placing HS-92-
5001 and HS-92-5002 SRM TRIP RESET-BLOCK handswitches
to BLOCK.
* Verify annunciator window XA-55-4A, C-1, is lit
* Select NR-45 to record 1 IR and 1 PR channel
* Adjust NR-45 chart speed as desired.
STANDARD: Acknowledge P*6 annunciator; Record SR and IR indications on MCB,
and verify IR indication > 1E,4%.
Places both switches in BLOCK, and observes annunciator XA-55-4A-C1
Selects one IR and one PR indication on NR-45
Cue: If the candidate reports t hat Sour ce Range High Flu x Tri ps have
been blocked, ackn owledge and prov ide direction t o raise reac to r
3
power t 01x1 0* % p ower t o o bt ain c riti cal data
COMMENTS:
JPM B.l.a
Page 8 of 10
RevO
Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
STEP 8. [63] Ensure PA announcement made to notify plant personnel when - SAT
the reactor is critical.
- UNSAT
STA NDARD: Announces criticality over the PA system
COMMENTS:
Note prior to step 64:
Whe n T-avg is less t han 551 degrees F and Tavg-Tref dev iation alarm Is lit, SR
4.1.1.4.b req uires ver ifying lowest T-AVG greater than or equ al to 541 deg rees F at
least once eve ry 30 minutes.
STEP 9. [64] If Tavg-Tref alarm (M-5A window C-6) is lit, and Tavg is less than - SAT
551 degrees F, Then perform 0-SI-SXX-068-127.0 to satisfy SR
4.1 .1.4.b, Minimum Temperature for Criticality. - UNSAT
STANDARD : Candidate verifies Tavg is 547 degrees F.
Cue: Another operator_will perform the surveillance
COMMENTS :
(
Booth Ins tructor: Insert malf unc tion IMF RD01 f:48 k:1 at t he next rod moti on.
Ind ication on 1-M-4, Rod Motion Red or Green Light.
STEP 10. [65] RAISE reactor power to approximately 1 X 10.3%: - SAT
[65.1] If Bank 0 rods are below fUlly withdrawn position, then operate - UNSAT
control rods to establish a positive SUR of approximately 0.5 DPM
(not to exceed 1 DPM)
STANDARD: Initiates rod withdrawal by placing IN-HOLD-OUT switch 1-HS-85- Critical Step
5111 to the OUT position. Ensures SUR is <1 DPM
COMMENTS :
JPM B.1.a
Page 9 of 10
Rev O
Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
STE P 11. Determines that Bank 0 Group 1 is stepping after releasing IN- - SAT
HOLD-OUT switch
- UNSAT
STAND ARD : Candidate reports rod movement to SRO or attempts to insert
Bank 0 rods . Determines rod movement does not stop
Cue : /f candidate reports to SRO, acknowledge the report. D/rect
the candidate to recommend an action
COMM ENTS:
STEP 12.: Trip the reactor in response to inappropriate continuous rod motion. - SAT
STAN DARD: Cand idate trips the reactor in response to inappropriate continuous rod - UNSAT
motion.
Note: Candidate may refer to AOP C.01 for tripping reactor Critical Step
COMM ENTS:
-
(
End of JPM
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMI NER UPON COMPLETION OF TASK)
DIRECT ION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All control room
steps shall be performed for this JPM, including any required communications. I will
provide initiating cues and reports on other actions when directed by you. Ensure you
indicate to me when you understand your assigned task. To indicate that you have
completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
A reac tor start up is in progress in accordance with 0-GO-2, Reactor Startup. The
following conditions exist:
* All shutdown bank rods are fully withd rawn .
* Con trol Bank "D" is at 127 steps.
* Th e estimated critical position is 155 steps on Control Bank "D". .
* Most Lecent 11M predicts 150 steps on Control Bank D
th
* You are at the 6 doubling of source range counts.
* All precautions, limitations, prerequisites and preceding steps for perfo rmance of
the task have bee n met or successfully performed.
INITIATING CUES:
The Un it Supervisor directs you to continue with the reactor startup and
withdraw control rods to criticality and increase power to take critical data
in accordance with 0-GO -2, Un it Startup from Hot Standby to Reactor
Critical, section 5.2, beginning at Step 55, and 0-50-85-1 section 6.3, step
41.
You are to notify the Unit Supervisor when critical data has been t aken.
- - - - -,,-._-,--_.. __._._-_ ..
Sequoyah Nuclear Plant
(
Unit 0
General Operat ing Instructions
O-GO-2
UNIT STARTUP FROM HOT STANDBY TO REACTOR CRITICAL
Revision 0026
Quality Related
Level of Use: Continuous Use
(
Effective Date: 12-10-2006
Responsible Organization: OPS, Operations
Prepared By: O. A. Porter
Approved By: W. T. Leary
Current Revision Description
Revised to resolve interface problem with 0-RT-NUC-000-003.0 (PER 115799). Added
contingency actions if Control Bank 0 reaches full out position. Incorporated various other
enhancements.
THIS PROCEDURE IMPACTS REACTIVITY
(
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
\ Paae 2 of 85
Table of Contents
1.0 FIRST SECTION 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 LIMITATIO NS 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 after a refueling outage 21
5.3 Reactor Startup after a non-refueling outage 45
6.0 RECORDS 69
Appendix A: DELETED 70
Append ix B: MODE 3 TO MODE 2,1 REVIEW AND APPROVAL 71
Ap pendi x C: DETERMING SOURCE RANGE COUNT RATE DOUBLI NG 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
SON UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
\"
Page 3 of 85
1.0 FIRST SECTION
1.1 Purpose
This General Operating (GO) Instruction provides necessary actions to perform a
unit startup from hot standby (Mode 3) to reactor critical (Mode 2) following a reactor
shutdown or initial startup after refueling.
1.2 Scope
A. This GO contains the following sections:
1. 5.1 Actions to perform prior to commencing reactor startup.
2. 5.2 Reactor startup after a refueling outage.
3. 5.3 Reactor startup after a non-refueling outage.
This instruction also provides guidance for the control of reactivity associated with
Xenon while the reactor is in a hot standby condition.
( 2.0 REFERENCES
2.1 Performance References
A. 0-RT-NUC-000-003.0, Low Power Physics Testing
B. 0-SI-OPS-000-004.0, Surveillance Requirements Petiormed on Increased
Frequency with No Specific Frequency
C. 0-SO-30-5, Lower Compartment Cooling Units
D. 0-SI-SXX-068-127.0, RCS and Pressurizer Temperature and Pressure Limits
E. 0-SO-30-6, Control Rod Drive Cooling Units
F. 1-PI-OPS-000-021 .1 , Mode 1-4 Control Room Operator MCR Duty Station Shift
Relief and Syst em Status Checklist
G. 2-PI-OPS-000-023.1 , Mode 1-4 Control Room Operator MCR Duty Station Shift
Relief and System Status Checklists
H. 1, 2-S0-3-2, Auxiliary Feedwater System
I. 1,2-SI-ICC-092-N41.1, Channel Calibration of Power Range Nuclear
Instrumentation System, Channel N4 1
---- - --
SQ N UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev . 0026
\. Paqe 4 of 85
2.1 Performance References (continued)
J. 1, 2-SI-ICC-092-N42.2, Channel Calibration of Power Range Nuclear
Instrumentation System, Channel N42
K. 1, 2-SI-ICC-092-N43 .3, Channel Calibration of Power Range Nuclear
Instrumentation System, Channel N43
L. 1,2-SI-ICC-092-N44.4, Channel Calibration of Power Range Nuclear
Instru mentation System, Channel N44
M. 0-SI-NUC-000-001.0, Estimated Critical Conditions
N. 0-SI-NU C-000-038.0, Shutdown Margin
O. 1, 2-SO-68-2, Reactor Coolant Pumps
P. 1-PI-OPS-057-001.0, Functional Testing of Low Voltage Bus Cooling Oil Pumps
Q. Core-Operating Limit Report
R. 0-PI-OPS-000-001.0, Initial Startup System Parameter Log
( S. 0-PI-OPS-301-001.0, Plant Computer Point Disablement
T. OPDP-4, Ann unciat or Disablement
U. SI-53, Specific Iodine Isotopic Activity Concentration and/or DE 1-131
Determination
V. SI-407.2, Radioactive Gaseous Waste Effluent Particulate and Iodine Dose
Rates from Shield and Auxiliary Building Exhausts (Weekly/ Special) and
Condenser Vacuum Exhaust (Special)
W. 0-SI-CEM-030-415 .0, Gaseous Effluent Requirements (Gross Alpha Noble Gas
and Tritium)
X. 0-SO-62-7, Boron Concentration Control
Y. 0-SO-85-1, Control Rod Drive and Rod Position Indication System
Z. OPDP-1, Conduct of Operations
AA. SPP-10.0, Plant Operations Standard Program
BB. SPP-3.1 , Corrective Action Program
CC. Technical Requirements Manual, 3.4.7
DO. Technical Specifications, SR 4.1.1 .4.a
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev, 0026
( Page 5 of 85
2.1 Performance References (continued)
EE. Technical Specifications, SR 4.1.1A.b
2.2 Developmental References
A, GO I-1, Plant Startup from Cold Shutdown to Hot Standby
B. GO I-2, Plant Startup from Hot Standby to Minimum Load
C, O-GO-2-1, Plant Startup from Hot Standby to Reactor Critical
D, FSAR Section 13,5
E, SPP-10 A , Reactivity Management Program
( \,
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Pa~e 6 of 85
3.0 PRECAUTIONS AND LIMITATIONS
3.1 PRECAUTIONS
A. Steps of this procedure must be performed sequentially , unless specifically
stated otherw ise.
B. Criticality is indicated by a positive stable startup rate (SUR) with no rod motion.
Anticipate criticality anytime reactivity changes are being made. Nuclear
instrumentation shall be monitored very closely in anticipation of unplanned
reactivity rate of change.
C. During the hot standby period, observe the source and intermediate range
instruments as the Xenon transient progresses to assure that an inadvertent
return to criticality does not occur.
D. Reactor Engineering should be contacted for guidance on core operating
recommendations during unusual power maneuvers such as startup at end of
coreJife. [C.8]
E. If reactor startup is anticipated prior to reaching the Xenon-free condition, the
( reactor coolant temperature, rod position, and boron concentration may be used
to account for time dependent changes in Xenon concentration. Conditions
should be close ly monitored to ensure that shutdown margin requirements of
0-SI-NUC-000- 038.0 are maintained at all times. If desired, shutdown rods may
be withdrawn in accordance with COLR specifications to provide immediate
insertion poison for a reactivity excursion. [C.12]
F. To preserve the life of 20 AST and 20 ET, power must be removed from the
turbine trip Bus A and trip bus B if unit startup is extended.
G. During the approach to criticality Operators shall not be distracted by activities
such as shift turnover and surveillance testing . [SQ99 0136PER]
H. US / SRO Oversight for control rod manipulation shall include :
1. Prior to Rod Movemen t
a. Ensure RPI's within T.S. range (+ or - 12 steps)
b. Verify on target with Rx Eng reactivity balance sheet
or withi n limits of Estimated Critical Condition (as appli cable)
c. Ensure procedural requirements met.
d. Ensure no simultaneous reactivity manipulations in progress.
\
_.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 7 of85
3.1 PRECAUTIONS (continued)
2. During Rod Movement
a. Ensure RO has peer check
b. Ensure RO is following procedure
c. Ensure RO 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-verify items 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. 0026
( Page 8 of 85
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
dete ctors 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 SUSPENDED IMMEDIATELY (i.e., 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 refue ling 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.3j - .
D. Whil e in Mode 3, maintain the Reactor Coolant System boron concentration in
( accordan ce 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 possibil ity of
CRDM mis-stepping due to crud contamination of CRDM latch assemblies.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paae 9 of 85
'"
STARTUP No. leo' Unit I Date ~cIay
4.0 PREREQUISITES
NOTES
1) Throughout this Instruction where an IF/THEN 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 .
[2] R~VIEW Precautions and Limitations.
INDICATE below which instruction this 80
( [3]
is being entered from:
* 0-GO-1 (cold shutdown to hot standby)
* 0-80-6 (30% reactor power to hot standby)
* 0-80-7 (hot standby to cold shutdown)
* 0-80-5 (normal power operation)
[4] MAINTAIN pressurizer pressure within the normal operating
band by use of the pressurizer heaters and spray valves .
[5] MAINTAIN pressurizer level greater than or equal to 25%.
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
Page 10 of 85
STARTUP No. Iill Unit I
4.0 PREREQUISITES (co ntinued)
NOTE
Due to instrument inaccuracies the steam dump or SG atmospheric relief valve setpoint of
84% or 1005 psig may be +/- 1% or +/- 12 psig off.
[6] MAINTAIN TAVG stable at 547°F with steam dumps
in pressure mode or with SG atmospheric relief valves.
[7] MAINTAIN SG levels within the normal operating range
using Auxiliary Feedwater.
[8] ENSURE all reactor coolant pumps are in operation in
aceordance with 1,2-S0 -68-2, Reactor Coolant Pumps. [C.12]
( [9] 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
followi ng checklists have been distributed:
[10.1] Mode 3 to Mode 2, 1, Surveillance Checklist
(NA if previously performed for this startup).
[1 0.2] 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).
[1 2] NOTIFY MIG to re-scale LR-3-43A and LR-3-98A, Steam
Generator Wide Range Level Recorders, to 80% - 90%.
\. ..
SQN UNIT STARTUP FROM HOT STANDBY 0*GO*2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 11 of 85
STARTUP No . /0/ Unit I Date~
4.0 PREREQUISITES (continued)
[13] ENSURE each performer documents their name and initials:
Print Name Initials Print Name Initials
:>. .t. f.I tt>- J'.m/"
t
-
(
END OF TEXT
\.
SON UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paae 12 of 85
STARTUP No. 11821 Unit I Date Tudry
5.0 INSTRUCTIONS
5.1 Actions to be performed prior to a reactor startup
[1] ENSURE Section 4.0. Prerequisites complete.
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 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 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/A if no MFPT available)
[5] ENSURE TDAFW LCVs are in NORMAL.
2fK AfIdP
1st IV
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 13 of 85
STARTUP No. /at::t U n it~/<--_ Date ~
5.1 Actions to be performed prior to a reactor startup (conti nued)
CAUTION
Rapid changes in pressurizer enclosure temperatu re may result in pressurizer safety
valve simmer.
[6] IF lower compartment coolers are not in service.
THE N
[6.1] ALIGN lower compartment coolers to maintain
pressurizer enclosure temperature less than 110°F
in accordance with 0-SO-30-5 .
[6.2] MONITOR Pressurizer enclosure temperature
_ using Plant Computer pt. T1001A.
( [7] IF control rod drive coolers are not in service,
THEN
[7.1 ] ALIGN control rod drive coolers to maintain
shroud enclosure temperature less than 164°F
in accordance with 0-SO-30-6.
[7.2] 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 chemistry has been changed.
[8] NOTIFY Chemistry Supervisor that mode change from 3 to 2
requires sampling in accordance with 0-SI-CEM-000-050.0.
0-SI-CEM-030-407.2, and 0-SI-CEM-030-415.0 requirements.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO*2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paae 14 of 85
STARTUP No. /4c:f Unit ~/,---_ Date 7<<IA.{
5.1 Actions to be performed prior to a reactor startup (continued)
NOTE
To prese rve 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 TRA IN BREAKER 250V DC POSITION INITIA LS
TRA IN A 1-BKRD-47-KA/516 BAIT Bd 1 CLOSED
RIle
1st
buR
CV
1
i lK IfW?
TRAIN B l- 1-BKRD-47-KB/516 BAITBd 2 CLOSED
* 1st CV
llh:- At",;
( 2
TRAIN A 2-BK RD-47-KA/519 BAIT Bd 1 CLOSED 1st CV
,;,nr
TRAIN B 2-BKRD-47-KB/519 BAITBd 2 CLOSED 1st
-*
NOTE
Step 5.1[10] may be marked N/A if not required.
[10] PERFORM 0-PI-OPS-047-723.0, 20/AS T, 20/ET, 20-1/0PC,
and 20-210 PC Operability Verification (N/A if not performed).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( "
Page 15 of 85
STARTUP No. IMI Unit 1 Date~
5.1 Actions to be performed prior to a reactor startup (con ti nued)
CAUTIO N
Operation of t he H ic pumps w ithout the t urbin e being reset w ill result in
overheating of the EHC fluid and pu mps.
NOTE
Startup of EHC and turbine reset may be postponed until later in startup, (N/A if
postponed )
[11] ENSURE EHC system in service in accordance with
1,2-5 0 -47-2 (NA if previously performed),
[12] IF 1'\0 MFPT is ready for start up per 1,2-8 0-2/3-1 ,
THEN
GO TO Section 5,1[18].
(
[1 3J 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 ,
J
'll~
sa<< /1Xf &c+---- 61n le-£
Initials Datr Time
SQN UNIT STARTUP FROM HOT STANDBY 0-GO*2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 16 of 85
STARTUP No. / tA:I Unit I Date 7 m411:\
5.1 Actions to be perform ed prior to a reac to r start up (cont in ued) I
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 LCO 3.0.4. [C.1]
2) Power is placed on only ONE MFPT trip bus in Step 5.1[14] to prevent inadvertent
AFW P start .
[14] ENSURE power restored to ONLY ONE of MFPT trip busses
on the applicable unit: (N/A breakers not applicable.) [C.1]
ELECTRICAL BREAKER
PUMP BREAKER NO. INITIALS
BOARD POSITION
250v DC MId Zj/tr
MFPT 1A 1-BKRD-46-KN523 Battery Bd I CLOSED 1st CV
(
~st
250v DC 'P
MFPT 1B 1-BKRD-46-KN524 Battery Bd I CLOSED CV
250v DC ;,-
MFPT 2A 2-BKRD-46-KB/523 Battery Bd 2 CLOSED
At/"
1s CV
250v DC 'b
MFPT 2B 2-BKRD-46-KB/524 Battery Bd 2 CLOSED Ht CV
--_._-- -
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paae 17 of 85
STARTUP No. 1(;(;)( Unit I Date ~
5.1 Actions to be performed prior to a reac tor startup (continued)
CAUTION
Failure to rese t a MFPT prior to energizing t he remaining MFPT trip buss will in itiate
an ESF actuation.
NOTE
If 51 signal or Hi/Hi stea m generator level has occurred, Reactor Trip Breakers will have to
be cycled .
[15] RESET MFPT energized in step 5.1[14] above.
~odtrx. 7rley
1st Time Date
CV
(
NOTE
IF the remaining NON-running MFPT is not available, THEN N/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)
ELECTRICAL BREAKER
PUMP BREAKER NO. INITIALS
BOARD POSITION
MFPT 1A 1-BKRD-46-KA/523
250v DC Battery
Bd I CLOSED
AJ{#
st
'9>
CV
250v DC Battery /'4' -II/f(£
MFPT 1B 1-BKRD-46-KA/524 Bd I CLOSED 1st CV
MFPT 2A 2-BKRD -46-KB/523
250v DC Battery
Bd 2 CLOSED
/1/11
1~t
'9
CfJ
250v DC Battery
MFPT 2B 2-BKRD- 46-KB/524 Bd 2 CLOSED 1st OV
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 18 of 85
STARTUP No. /(D I Unit I Date 7dJ~
5.1 Ac tions to be performed prior to a reactor startup (continued)
[17] RESET MFPT energized in step 5.1 [16] above.
_--Ji'M:'----_ _ &A1ti!q
1st Time 'fJ~7
Date
CV
00In
Time
[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 is in operation and selected
for source range channel with highest reading. [C.1 1]
[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.5]
NOTE
Closing of the RTB's for performance of 0-SI-OPS-085-01 1.0 (SR 4.1.3.3) is addressed in
Licensing and NRC TelephoneNisit Report RIMs # S10 960521 800.
[22] IF 0-SI-OPS-085-011.0 is out-of-frequency,
THEN
[22.1] CLOSE RTB's provided Group Demand counters have
no known deficiencies. Q""'"
[22.2] PERFORM 0-SI-OPS-085-011.0 (NA if above step
cannot be performed).
saN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 19 of 85
STARTUP No. /Ql)1 Unit I Date~
5.1 Actions to be periormed prior to a reactor startup (continued)
[23] IF control rods were withdrawn 5 steps to prevent thermal
lockup during RCS 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.
[24.2] DEPRESS ROD BANK UPDATE Button
AND
ENSURE all bank positions are zero.
[24.3] _ DEPRESS F3 to save these rod bank positions.
[25] VERIFY Rod Bank Update status by performing the following:
(
[25.1] DEPRESS NSSS and BOP button on ICS main screen.
[25.2] DEPRESS ROD INSERTION LIMIT DISPLAY Button.
[25.3] VERIFY Rod Bank Update Status indicates "UPDATED"
in green letters.
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
FROM : SEQUC YAH OPERATOR TRA I NI NG PHONE NO. 423 843 4339 Hpr-, 04 2007 02 : 00PM P3
( saN UNIT STARTUP FROM HOT STANDBY 0-GO-2
.r --, UnitO TO REACTOR CRITICAL Rev. 0026
PaCle 26 of 85
STARTUP No. /()c) I Uni t ' Date~
5.2 Reactor Startup after a refueling outage (continued)
I CAUTION
~) NOT exceed a steady startup rate of +1 DPM.
I
~ NOTE
l~l1e unit enters Mode 2 when the control banks are first withdrawn.
II
[17] INITIATE a reactor startup by performing the following:
[17.1] . RECORD both source range readings
for ICRR base counts.
N-31 .2~ CPS N-32 /1 CPS Lk
Initials
( [17.2] RECORD intermediate range readings.
N-35/..3X(~~10 N-36Plxt,*f, -2IIIL-
Initials
[1 7,3J CALCULATE initial source range count doubling value
USING Appendix C.
MODE 2
[17.4] INITIATE withdrawal of control banks in accordance
with o-SO-85-1 t o first stop' point:
_ CONTROL
_ _- BANK -A- - I 128 STEPS .J
[17.5] ENSURE Mode 2 entry is logged
(log entry may be performed out of sequence late-) , o
*'
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
( Unit 0 TO REACTOR CRITICAL Rev. 0026
Pa!le 26 of 85
STARTUP No. ,/()p{ Unit /
5.2 Reactor Startup after a refuel ing outage (continued)
CAUTION
Do NOT exceed a steady startup rate of +1 DPM.
NOTE
The unit enters Mode 2 when the cont rol banks are first withdrawn.
[17] INITIATE a react or startup by perform ing the following :
[17.1] RECORD both source range readings
for ICRR base co unts.
N-31{.27~CP5 N-32/$oc)CP5 .?/Ie:
Initials
[17.2] RECORD inte rmediate range readings .
(
N-35 t 3k ~~fo N-36 t4",rfo &tr
Initials
[17 .3] CALCULATE initial source range count doubling value
USING Append ix C.
MODE 2
[17.4] INITIATE withdrawal of control banks in acco rdance
with 0-50-85-1 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. 0026
Page 27 of 85
STARTUP No. IIXJ! Unit_-s-_I Date~
5.2 Reactor Startup afte r a refueling outage (continued)
[18] WHEN control bank A is at 128 steps,
THEN
PERFORM the following:
[18.1] STOP rod withdrawal.
[1 8.2] WAIT for approximately two minutes.
[18.3] NOTIFY Rx Engineering to perform ICRR calculation
in accordance with 0-RT-NUC-000-003.0. [C.11]
CAUTIO N
Lowest loop T*avg mus t be verified greater than or equ al to 541°F
using 0*SI-SXX*068-127.0 within 15 minutes prior to achieving cr iticality.
( NOTES
1) 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 withdrawa l to first count doubling
(determined in App. C) USING 0-80-85-1.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
Pace 28 of 85
\ ..
STARTUP No. /<<';1 I
Unit_--L.._ Date~
5.2 Reactor Startup afte r a refuel ing outage (con tinued)
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 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 0-8 0-85-1.
[22] IF source range count rate has reached or exceeded
first doubling,
THEN
PERFORM the following:
[22.1] ENSURE rod motion STOPPED. nrti
*
[22.2] WAIT approximately 2-3 minutes
to allow count rate to rise.
[22.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with O-RT-NUC-000-003.0. [C.11]
[22.4] DETERMINE new count doubling range
USING Appendix C.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Uni t 0 TO REACTOR CRITICAL Rev. 0026
Page 29 of 85
STARTUP No. ,Ity;( Unit_.L-_ I Date~
5.2 Reactor Startup after a refueling outage (continued)
[23] IF IGRR plot indicates criticality will fall outside
+/- 1000 pcm EGG termination band,
THEN
[23.1 ] NOTIFY SM and Duty Plant Manager.
[23.2] EVALUATE if EGG should be recalculated
prior to continuing startup.
[23.3] IF startup must be aborted,
THEN ~
PERFORM Appendix D, Actions if Reactor Startup Must
Be Aborted. ' '-J
f-1
[24] WI:IEN concurrence obtained from Rx Engineering,
THEN
INITIATE rod withdrawal to second doubling range
( (determined in App. G) USING 0-SO-85-1.
NOTE
Steps 5.2[25] and 5.2[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 G
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.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL
c Rev. 0026
Page 30 of 85
STARTUP No. / cal Unit_4-_ I
5.2 Reactor Startup after a refueli ng outage (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,
THEN
PERFORM the following:
[27.1] ENSURE rod motion STOPPED. WE
*
[27.2] WAIT approximately 2-3 minutes
_ to allow count rate to rise.
[27.3] NOTIFY Rx Engineering to perform ICRR calculations in
c [27.4]
accordance with 0-RT-NUC-000-003.0. [C.11]
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 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.
[29] IF ICRR plot trend indicates acceptable ECC,
THEN
INITIATE rod withdrawal to third doubling range
(determined in App. C) USING 0-SO-85-1.
\..
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 31 of 85
STARTUP No. IfX;JI Unit I
5.2 Reactor Startup after a refueling outage (continued)
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 dete rmined 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 doub ling 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.
[32.3] NOTIFY Rx Engineering to perform le RR calculations in
accordance with 0-RT-NUC-000-003.0. [C.11]
[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. 0026
( Paqe 32 of 85
STARTUP No. --I..Od.- Unit I
*
5.2 Reactor Startup after a refueling outage (continued)
[33] IF ICRR plot indicates criticality will fall outside
+/- 1000 pcm ECC termination band,
THEN
[33.1] NOTIFY SM and Duty Plant Manager.
[33.2] EVALUATE if ECC should be recalculated
prior to continuing startup.
[33.3] IF startup must be aborted,
THEN
PERFORM Appendix D, Actions if Reactor Startup Must if'
Be Aborted. r:!
[34] IF ICRR plot trend indicates acceptable ECC,
THEN
INITIATE rod withdrawal USING 0-SO-85-1
to fourth doubling range (App. C) or criticality.
( NOTE
Steps 5.2[35] through 5.2[37] may be repeated as necessary if rod motion is stopped
prior to reaching doubling range or criticality.
[35] WHEN any of the following conditions are mel:
* 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
* . Operators or Rx Engineer determine that rod motion
should be stopped
THEN
STOP outward rod motion.
- - - - - --
SON UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 33 of 85
STARTUP No. ~ Unit I Date /(; " " ;
5.2 Reactor Startup after a refueling outage (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). ~D 0 0
( [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.
[38.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with 0-RT-NUC-000-003 .0. [C.11]
[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
~
~0
Rods Fully Withdrawn.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 34 of 85
STARTUP No. /0l?I Unit I Date~
5.2 Reactor Sta rtup after a refue li ng ou tage (continued)
[40] IF ICRR plot indicates criticality will fall outside
+/- 1000 pcm ECC termination band,
THEN
[40.1] NOTIFY SM and Duty Plant Manager.
[40.2] EVALUATE if ECC should be recalculated
prior to continuing startup.
[40.3] IF startup must be aborted,
THEN
PERFORM Append ix D, Actions if Reactor Startup Must
Be Aborted.
[41] IF I.9RR plot trend indicates acceptable ECC,
THEN
INITIATE rod withdrawal USING 0-SO-85-1
( to fifth doubling range (App. C) or criticality.
NOTE
Steps 5.2[42] through 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 C
OR
* Bank D rods reach fully withdrawn position
OR
* 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]).
SQN UNIT STARTUP FRO M HOT STANDBY 0-GO-2
UnitO TO REACTOR CRITICAL Rev. 0026
( Pace 35 of 85
STARTUP No. / cht Unit I Date /do"7
5.2 Reactor Startup after a refuel ing outage (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 obta ined to resume,
THEN
RESUME rod withdrawal USING 0-SO-85-1
to fifth doubling range or criticality (whicheve r 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.
[45.3] NOTIFY Rx Engineering to perfo rm leRR calculations in
accordan ce with 0-RT-NUC-000 -003 .0. [C.11]
[45.4] DETERMINE new count doub ling range
USING Appendix C.
[46] IF reactor is subcritical with Bank D rods
at fully withdrawn position,
THEN
PERFORM Appendi x E, Actions if Reactor is Subcritical with
Rods Fully Withdrawn .
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 36 of 85
5.2
STARTUP No. L@_ Unit
Reactor Startup after a refueling outage (continued)
I Date 4
[47] IF IGRR plot indicates criticality will fall outside
+/- 1000 pcm EGG termination band,
THEN
[47.1] NOTIFY SM and Duty Plant Manager.
[47.2] EVALUATE if EGG 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 .
[48] IF IGRR plot trend indicates acceptable EGG,
THEN
INITIATE rod withdrawal USING 0-SO-85-1
to sixth doubling range (App. C) 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 of the following conditions are met:
* Source range count rate reaches or exceeds
sixth doubling range determined in Appendix C
OR
* Bank D rods reach fully withdraw n position
OR
* 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]).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 37 of 85
STARTUP No. / t?i'J1 Unit I Date /dcla
5.2 Reactor Startup after a refueling outage (continued)
i
[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-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.
[52.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with 0-RT-NUC-000-003.0. [C.11)
[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.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
UnitO TO REACTOR CRITICAL Rev. 0026
( Pace 38 of 85
STARTUP No. [(J()( Unit I
5.2 Reactor Startup after a refuel ing outage (co ntinued)
[54] IF IGRR plot indicates criticality will fall outside
+/- 1000 pcm EGG termination band,
THEN
[54.1] NOTIFY SM and Duty Plant Manager.
[54.2] EVALUATE if EGG should be recalculated
prior to continuing startup.
[54.3] IF startup must be aborted, THEN
PERFORM Appendix D, Actions if Reactor Startup Must
Be Abo rted.
[55] IF IGRR plot trend indicates acceptable EGG,
THE N
INITIATE rod withdrawal USING 0-SO-85- 1
to seventh doubling range (App. C) or criticality. o
( 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
* Operators or Rx Engineer determine that rod motion
should be stopped
THEN
STOP outward rod motion. DODD
[57] IF reacto r is critical,
THEN
GO TO Step 5.2[59] (N/A Step 5.2[58]).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 39 of 85
STARTUP No. _ Unit _ Date _
5.2 Reactor Startup aft er a refuel ing outage (continued)
[58] 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 seventh doubling range or criticality (whichever comes first). 0 0 0 0
[59] IF any of the following conditions exist:
* - critical conditions cannot be achieved
within the +/-1000 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. o
[59.4] DO NOT CONTINUE this section.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 40 of 85
STARTUP No. Unit _ Date _
5.2 Reactor Startup after a refueling outage (continued)
[60] 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
[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 0 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. 0.3 DPM
USING 0-SO-62-7.
c....
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 41 of 85
STARTUP No. _ Unit _ Date _
5.2 Reactor Startup after a refueling ou tage (continued)
IStart of Critical Step(s)
NOTES
1) Blocking the SRM reactor trip with [HS-92-50011 and [HS-92-50021 will disable the
detect or 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 0 -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 to 1 X 10 -4 % RTP. o
[62.4] BLOCK source range reactor trip by momentarily
placing [HS-92-50011 and [HS-92-50021 SRM TRIP
RESET-BLOCK P-6 handswitches to BLOCK.
Initials Date Time
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
(.. Page 42 of 85
STARTUP No. _ Unit _ Date _
5.2 Reac tor Startup after a refuel ing outage (continued)
[62.5] VERIFY annunciator XA-55-4A, window C-1
SOURCE RANGE
TRAINS A & B TRIP
BLOCK is LIT.
o
IEnd of Critica l Step(s)
[62.6] SELECT NR 45to record one intermediate range
channel and one power range channel.
[62.7] ADJUST NR 45 chart speed as desired.
(N/A is no change needed.) o
[63] ENSURE PA announcement made to notify plant personnel
when the reactor is critical. o
NOTE
Wh en 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. 0026
( Page 43 of 85
STARTUP No . _ Unit _ Date _
5.2 Reactor Startup after a refueling outage (continued)
[65) RAISE reactor power to approximately 1 X 10-3% :
[65.1) IF Bank 0 control rods are BELOW
fully withdrawn position,
THEN
OPERATE control rods to establish a positive SUR
of approximately 0.5 OPM (not to exceed 1 OPM).
[65 .2) IF Bank 0 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 Nls indicate
appro ximately 1 X 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: N-35_ _ %RTP N-36_ _ %RTP
Rod Position: RCS Boron concentration
Bank Step ppm
1 2 3 4
Initials Date Time
[66J MAINTAIN reactor power stable with control banks
above low insertion limit 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. 0026
( Pane 44 of 85
STARTUP No. _ Unit _ Date _
5.2 Reactor Startup after a refue ling outage (continued)
[67] IF start up is to continue with one or both MFPTs available,
THE N
[67.1] ENSURE Steps 5.1 [13] through 5.1[15] have been
comp leted for applicable pump(s).
[67.2] VERIFY other applicable actions Section 5.2 completed
or initiated .
[67.3] GO TO 0-GO-3, Power Ascension From Reactor Critical
to Less Than 5% Reactor Power.
[68] IF start up is to continue with NO MFPT available,
THEN
[68.1] MARK Steps 5.1[13] through 5.1[17] as 'O N/A".
[68.2] VERIFY other applicable actions in Section 5.2
completed or initiate d.
[68.3] GO TO 0-GO-3 , Power Ascension From Reactor Critical
to Less Than 5% Reactor Power.
[69] IF startup is to be discontinued ,
THEN
GO TO 0-GO-6, Power Reduction From 30% Reactor Power to
Hot Standby.
END OF TEXT
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
c Unit 0
STARTUP No .
TO REACTOR CRITICAL
_ Unit _
Rev. 0026
Paae 45 of 85
Date _
5.3 Reactor Startup after a non-refueling outage
[1] VERIFY applicable actions in Section 5.1 completed or
initiated.
NOTE
Steps 5.3[3] through 5.3[8] may be performed out of sequence.
[2] IF any MFPT trip buss is NOT energized ,
THEN
[2.1] ENSURE requirements of LCO 3.0.4 are satisfied .
[2.2] NOTI FY Unit SRO 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 appro vals for mode
change gra nted.
SM
[4] BLOCK Source Range High Flux At Shutdown alarm:
[4.1] PLACE BOTH HI FLUX AT SHUTDOWN switches
on M-13 to the BLOCK positio n.
[4.2] VERIFY annun ciator XA-55-4 B window C-1,
SOURCE RANGE
HIGH SHUTDOWN
FLUX ALARM is L1T.[C.2].
CLOCK
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. 0026
( Paae 46 of 85
STARTUP No. _ Uni t _ Date _
5.3 Reac to r Startup after a non -ref ueli ng outage (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) (N/A instruments not used)
XI-92-5001A (N31) cps
XI-92-5002A (N32) cps
OR
XI-92-5001B (N31) _ _ _ cps
XI-92-5002B (N32) _ _ _ _cps
Time Date
( [7) IF conditions exist which could cause Power Range NIS
indicatio ns to be non-conservative,
THE N
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. 0026
( Page 47 of 85
STARTUP No . _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (con tinued)
[8) VERIFY the estimated critical position calculated in
accordance with 0-8 1-NUC-000-001.0, Estimated Critical
Conditions.
Estimated critical position: steps on bank
Assumed boron concentration: ppm
Initials Time Date
8TA Time Date
[9] VERIFY Steps 5.3[1] through 5.3[8) completed.
[10] IF estimated critical boron concentration does NOT
approximate ly 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] D
[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
[10.4] 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.
(
saN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 48 of 85
STARTUP No . _ Unit _ Date _
5.3 Reac to r Startup after a non-refueling outage (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
termi nated and a new ECC calculated . ECC must be terminated if Minimum or Maximum
Allowable Limits (correspo nding to Tech Spec limit of +/- 1000 pcm) are approached.
[11] RECORD upper and lower rod positio n limits correspondi ng to
+/- 750 pcm Termination Band as determined by
0-SI-N UC-000-001 .0. Estimated Critical Conditions .
Upper termination rod position steps on bank
Lower termination rod position steps on bank
( Initials Time Date
[12] RECORD minimum and maximum rod positions correspo nding
to +/- 1000 pcm ALLOWAB LE LIMITS (Tech Spec Limit)
determined by 0-SI-NUC-000 -001.0, Estimated Critical
Conditions. [C.11]
Minimum allowable rod position steps on bank
Maximum allowable rod positio n steps on bank
Initials Time Date
[13] VERIFY all shutdown rods are fully withdrawn in accordance
with 0-SI-OPS-000-004.0. Surveillence Requirements
Performed on Increased Frequency with no Specific
Frequency, within 15 minutes prior to withdrawing control rods.
Time Date
(
SON UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 49 of 85
STARTUP No. _ Unit _ Date _---'__
5.3 Reactor Startup afte r a no n-refue ling outage (co nti nued)
NOTE
SR 4.1.1.4.a requires verifying lowest T-avg greater than or equal to 541°F
withi n 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. 0
CAUTION
Avoid operatio ns tha t could produce sudden changes of temperatu re or unplanned
boron con cen tration changes du ring approach to cr iticality 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 range and intermediate range NIS
to identify potential reactivity anomalies . [C.11] o
[16.2] IF desired to place NR-45 recorder in fast speed,
THEN
ADJUST chart speed to high.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 50 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startup aft er a no n-refueli ng ou tage (continued)
CAUTION
Do NOT exceed a steady sta rtup rat e of +1 DPM.
NOTE
The unit ente rs 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 leRR base counts.
N-31_ _CPS N-32,_ _CPS
Initials
[17.2] RECORD intermedi ate range readings.
N-35 % N-36 %
Initials
[17.3] CALCULATE initial source range count doub ling value
USING Appendix C.
MODE2
[17.4] INITIATE withdrawal of control banks in acco rdance
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
Uni tO TO REACTOR CRITICAL Rev. 0026
( Pane 51 of 85
STARTUP No. _ Uni t _ Date _
5.3 Reactor Startup after a non-refueling outage (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] NOTIFY Rx Engineering to perform ICRR calculation
in accordance with 0-81-NUC-000-001.0. [C.11]
CAUTION
Lowest loop T-avg must be ver ified greater t han or equal to 541 °F
us ing 0-SI-SXX-068-127.0 withi n 15 minutes prior to achieving criticality.
NOTES
1) Appro ximately 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,
THE N
INITIATE rod withdrawal to first count doubling
(dete rmined in App. C) USING 0-80-85-1. o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
UnitO TO REACTOR CRITICAL Rev . 0026
( Pace 52 of 85
STARTUP No. _ Un it _ Date _
5.3 Reacto r Startup after a non-refueling outage (continued)
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 condit ions are met:
* Source range count rate is approximate ly 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 or Rx Engineer determine that rod motion
should be stopped
THEN
STOP outward rod motion. DODD
[21) IF rod motion was stopped prior to reaching doubling range
AND Unit Supervisor concu rrence is obtai ned to resume,
THEN
RESUME rod withdrawal to first count doubling
USING 0-SO-85-1 . DO DD
[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 .
[22.3) NOTIFY Rx Engineering to perform ICRR calculations in
acco rdance with 0-SI-NUC-000-001 .0. [C.1 1] 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. 0026
( Page 53 of 85
STARTUP No . _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (continued)
[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.
[23.3] IF startup must be aborted,
THEN
PERFORM Appendix D, Actions if Reactor Startup Must
Be Aborted. 0
[24) WHEN concurrence obtained from Rx Engineering,
THE;.N
INITIATE rod withdrawal to second doubling range
(determined in App. C) USING 0-SO-85-1. o
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
* 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. 000 0
(
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Un itO TO REACTOR CRITICAL Rev. 0026
( Page 54 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (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. 0000
[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-SI-NUC-000-001.0. [C.11] 0
[27.4] DETERMINE new count doubling range
USING Appendix G.
[28] IF IGRR plot indicates criticality will fall outside
+/- 750 pcm EGG 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. 0
[29] IF IGRR plot trend indicates acceptable EGG,
THEN
INITIATE rod withdrawal to third doubling range
(determined in App. G) USING 0-SO-85-1. o
SON UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 - TO REACTOR CRITICAL Rev. 0026
(-. Page 55 of 85
STARTUP No . _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (conti nued)
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. DODD
[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 0-8 0-85-1. 0000
[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.
[32.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with 0-SI-NUC-000-001.0. [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. 0026
('.
Page 56 of 85
STARTUP No. _ Unit _ Date _
5.3 Reac tor Startup after a non-refueling outage (co ntinued)
[33] IF ICRR plot indicates criticality will fall outside
+/- 750 pcm ECC termination band,
THEN
[33.1] NOTIFY SM and Duty Plant Manager.
[33.2] EVALUATE if ECC 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 ECC,
TH_EN
INITIATE rod withdrawal USING 0-SO-85-1
to fourth doubling range (App. C) or criticality. o
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 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
* Operators or Rx Engineer determine that rod motion
should be stopped
THEN
STOP outward rod motion. 0000
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2
Unit 0 TO REACTOR CRITICAL RevoOO26
( Paqe 57 of 85
STARTUP No, _ Unit _ Date _
503 Reactor Startup after a non-refueling outage (continued)
[36] IF reactor is critical,
THEN
GO TO Step 5.3[59] (N/A Steps 5.3[37] through 5.3[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). 0000
[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] WA IT approximately 2-3 minutes
to allow count rate to rise.
[38.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with 0-SI-NUC-000-001.0. [C011] 0
[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 Withdraw n. 0
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
c Unit 0
STARTUP No.
TO REACTOR CRITICAL
Unit _
Rev. 0026
Page 58 of 85
Date _
5.3 Reactor Startup after a non-refueling outage (continued)
[40] IF IGRR plot indicates criticality will fall outside
+/- 750 pcm EGG termination band,
THEN
[40.1] NOTIFY SM and Duty Plant Manager.
[40 .2] EVALUATE if ECG should be recalculated
prior to continuing startup.
[40.3] IF startup must be aborted,
THEN
PERFORM Appendix D, Actions if Reactor Startup Must
Be Aborted. 0
[41] IF IGRR plot trend indicates acceptable EGG,
TH_EN
INITIATE rod withdrawal USING 0-SO-85-1
to fifth doubling range (App . G) or criticality. o
NOTE
Steps 5.3[42] thro ugh 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 G
OR
* Bank D rods reach fully withdrawn position
OR
* Operators or Rx Engineer determine that rod motion
should be stopped
THEN
STOP outward rod motion. DODD
[43] IF reactor is critical,
THEN
GO TO Step 5.3[59] (N/A Steps 5.3[44] through 5.3[58]).
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 59 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startu p after a non-refu eling outage (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 concur rence is obtained to resume,
THEN
RESUME rod withdrawal USING 0-80-85-1
to fifth doubling range or criticality (whichever comes first). 0000
[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.
[45.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with 0-SI-NUC-000-001 .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
l
SON UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 60 of 85
STARTUP No . Unit _ Date _
5.3 Reactor Startup after a non-refueling ou tage (continued)
[47] IF ICRR plot indica tes criticality will fall outside
+/- 750 pcm ECC termination band ,
THEN
[47 .1] NOTIFY SM and Duty Plant Manager.
[47 .2] EVALUATE if ECC should be recalculated
prior to continuing startup.
[47 .3] IF startup must be aborted ,
THEN
PERFORM Ap pendix D, Actions if Reactor Startup Must
Be Aborted . 0
[48] IF ICRR plot trend indicates acceptable ECC,
THE N
INITIATE rod withd rawa l USING 0-SO-85- 1
to sixth doubling range (App. C) or criticality. o
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 doublin g range determined in Appe ndix C
OR
* Bank D rods reac h fully withdrawn position
OR
* Operators or Rx Engineer determ ine that rod motion
should be stopped
THEN
STOP outward rod moti on. 0000
[50] IF reactor is critical,
THEN
GO TO Step 5.3[59] (N/A Steps 5.3[51] through 5.3[58]).
(,
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( PaQe 61 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startup afte r a non-refueling outage (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-SO-85-1
to sixth doubling range or criticality (whichever comes first). D D D D
[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.
[52.3] NOTIFY Rx Engineering to perform ICRR calculations in
accordance with O-SI-NUC-OOO-001.0. [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
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( Page 62 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startup afte r a non-refueli ng outage (continued)
[54] IF ICRR plot indicates criticality will fall outside
+/- 750 pcm EGG termination band,
THE N
[54.1] NOTIFY SM and Duty Plant Manager.
[54.2] EVALUATE if EGC should be recalculated
prior to continuing startup.
[54.3] IF startup must be aborted ,
THEN
PERFORM Appendix D, Actions if Reactor Startup Must
Be Aborted. D
[55] IF IGRR plot trend indicates acceptable EGG,
Tf-i!:N
INITIATE rod withdrawal USING 0-SO-85-1
to seventh doubling range (App. G) or criticality. D
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 G
OR
* Bank D rods reach fully withdrawn position
OR
* Operators or Rx Engineer determine that rod motion
should be stopped
THEN
STOP outward rod motion. D D D D
[57) IF reactor is critical,
THEN
GO TO Step 5.3[59] (N/A Step 5.3[58]).
(
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 63 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startup aft er a non-refueling outage (contin ued)
[58] 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 seventh doubling range or criticality (whichever comes first). 0 0 0 0
[59) IF any of the following conditions exist:
* - critical conditions cannot be achieved
within the +/-750 pcm termination band
OR
* critical conditions cannot be achieved
within the +/-1000 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 0 , Actions if Reactor Startup
Must Be Aborted. o
[59.4) DO NOT CONTINUE this section.
l
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STARTUP No. _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (continued)
[60] IF reactor is subcritical with Bank 0 rods
at fully withdrawn position,
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 P-6 (1 X 10-4 %),
THEN
PERFORM the following:
[61.1] IF Bank 0 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 0 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. 0.3 DPM
USING 0-SO-62-7.
SQN UNIT STARTUP FROM HOT STANDBY 0*GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
c Page 65 of 85
STARTUP No. Unit _ Date _
5.3 Reactor Startup afte r a non-refueling outage (continued)
ISta rt of Critical Step(s)
NOTES
3) Blocking the SRM reactor trip with [HS-92 -50011 and [HS-92-5002] 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 105 cps.
[62] WHEN annunciator XA-55-4A , window D-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 IRM channel greater than or
equal to 1 X 10.4 % RTP. 0
[62.4] BLOCK source range reactor trip by momentarily
placing [HS-92-5001] and [HS-92-5002] SRM TRIP
RESET-BLOCK P-6 handswitches to BLOCK.
Initials Time Date
SQN UNIT STARTUP FROM HOT STANDBY O-GO-2
UnitO TO REACTOR CRITICAL Rev. 0026
( Paqe 66 of 85
STARTUP No. _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (continued)
[62.5] VERIFY annunciator XA-55-4A, window C-1
SOURCE RANGE
TRAINS A & B TRIP
BLOCK is LIT.
o
IEnd of Critical Step(s)
[62.6] SELECT NR 45 to record one intermediate range
channel and one power range channel. o
[62.7] ADJUST NR 45 chart speed as desired.
_ (N/A if no change needed). o
[63] ENSURE PA announcement made to notify plant personnel
when the reactor is critical. o
NOTE
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. 0026
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STARTUP No. _ Unit _ Date _
5.3 Reactor Startup after a non-refueling outage (continued)
[65) RAISE reactor power to approximately 1 X 10.3 'Yo:
[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 0 rods have reached fully withdrawn position
AND Rx Engineering concu rs 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
approximately 1 X 10.3 'Yo,
THEN
PERFORM the following :
[65 .3.1) STABILIZE reactor power using control rods.
[65.3.2] RECORD critical data indicated below.
Powe r Level: N-35 %RTP N-36 %RTP
Rod Position: RCS Boron concentration
Bank Step ppm
Loop TAVG;
1 2 3 4
Initials Time Date
[66] VERIFY control rods above rod insertion limit
USING 1,2-SI-OPS-000-002.0, Shift Log. o
[67) MAINTAIN reactor power stable with control banks
abo ve low insertion limit USING rod movement or
boration/dilution to compen sate for Xenon. o
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
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( Page 68 of 85
STARTUP No. _ Unit _ Date _
5.3 Reacto r Startup after a non-refuel ing outage (continued)
[68) IF start up is to continue with one or both MFPTs available,
THEN
[68.1) ENSURE Steps 5.1[13] throug h 5.1[15) have been
completed for applicable pump(s).
[68.2] VERIFY other applicable actions in Section 5.3
completed or initiated .
[68.3] GO TO 0-GO-3, Power Ascension From Reactor Critical
to Less Than 5% Reactor Power.
[69) IF start up is to continue with NO MFPT available ,
THEN
[69.1] MARK Steps 5.1[13) through 5.1[1 7] as "N/A".
[69.2] VERIFY other applicable actions in Section 5.3
compl eted or initiated .
[69.3) GO TO 0-GO-3, Power Ascension From Reactor Critical
to Less Than 5% Reactor Power.
[70] IF startup is to be discontinued,
THE N
GO TO 0-GO-6, Power Reduction From 30 %
Reactor Power to Hot Standby.
END OF TEXT
saN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( 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
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( Page 70 of 85
Appendix A
(Page 1 of 1)
DELETED
1.0 DELETED
(
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( Paqe 71 of 85
'.
Appendix B
(Page 1 of 8)
MODE 3 TO MODE 2,1 REVIEW AND APPROVAL
STARTUP No. Unit _ Date _
1.0 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
follo wing:
NOTE
Mode 3 to Mode 2, 1 Checklist and Reactor Trip Breaker Checklist are to be attached to
this instruction .
A. Mode 3 to Mode 2,1 Checklists from the respo nsible
sections and DETERMINE that the requi red surveillance
testing for Mode 2 entry has been comp leted .
Time Date
B. Reactor Trip Breaker Closure Checkl ists from the
responsible sections and DETERMINE that required
surveillance testi ng for mode change has been
comp leted .
Time Date
C. Active clearances for mode change restraints. [C .10].
Time Date
D. TACF Books for outstanding alternations on systems prior
to declaring a T .S. system or compo nent operable . [C.10]
Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paae 72 of 85
Appendix B
(Page 2 of 8)
STARTUP No. Unit _ Date _
1.0 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 change.
Time Date
F. Active Procedures Book to determine equipment status
that may be abnormal.
Time Date
G. OPDP-4, Annunciator Disablement Log for alarms
affecting operability of equipment required for mode
change .
Time Date
H. O-PI-OPS-301-001.0 Plant Computer Point Disablement
Log for alarms affecting operability of equipment required
for mode change.
Time Date
I. Board walkdown is completed to verify proper equipment
alignment.
(Refer to appropriate CRO and OATe Pis for guidance)
[C.10]
Time Date
- --- ---------
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
c Unit 0 TO REACTOR CRITICAL
Appendix B
Rev. 0026
Page 73 of 85
(Page 3 of 8)
STARTUP No. Unit _ Date _
1.0 MODE 3 TO 2,1 REVIEW AND APPROVAL (continued)
NOTE
Tech Spec and T RM LCO 3.0.4 govern entering Mode 2 if any LCO requirement applicable
in Mode 2 is not met. Therefore , mode change is not allowed while in a Tech Spec or
TRM action UNLESS the exceptions and/or allowances stated in LeO 3.0.4 can be applied.
J. REVIEW all Tech Spec and TRM Actions which have
been entered on the affected unit and common equipment
to verify that mode change is acceptab le.
SRO Time Date
SRO Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0*GO-2
UnitO TO REACTOR CRITICAL Rev. 0026
( Page 74 of 85
Append ix B
(Page 4 of 8)
STARTUP No. Unit _ Date _
2.0 DEPARTMENT MANAGERS REVIEW
2.1 Period ic Tes t Coordinator:
[1] ENSURE that all surveillance requirements for mode 2 entry
are updated and included within the mode change check list.
Periodic Test Coordinator Time Date
[2] ENSURE that all surveillance requirements for Reactor Trip
Breaker Closure Checklist are updated and included within the
checkl ist. [C.9)
Periodic Test Coordinator Time Date
2.2 Instrument Maintenance:
[1] ENSURE Wide Range SG Level Recorders [LR-3-43A) and
[LR-3 -98A) are OPERABLE and SET to a range requested by
the operator. (Recommended range between 80 and 90% of
scale). [C.6]
Instrument Maintenance Time Date
2.3 Fire Ops Section:
[1] ENSURE limitations as stated in 0-TI-SXX-000-016.0 are not
exceeded .
Fire Manager or Designee Time Date
l
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Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paae 75 of 85
Appendix B
(Pag e 5 of 8)
STARTUP No . _ Unit _ Date _
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 Time Date
[2) REVIEW of Reactor Trip Breaker Closure Checklist is
complete, all surveillance requirements have met their
accep tance criteria , and all open items that affect mode
change have been closed .
Shift Manager Time Date
NOTE
Th e 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 .
System Engineering Time Date
[4) IF startup is following a refueling outage ,
THEN
ENSURE Present Cycle Core Operating Limit Report are
inserted in the unit's Technical Specification Binder. [C.7)
Licensing or designee Time Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 76 of 85
Appe ndix B
(Page 6 of 8)
STARTUP No. _ Unit _ Date -r-
2.5 Maintenance Section:
[1 ] REVIEW of mode change checklist is complete and all
surveillance requirements have met their acceptance criteria
for Mode 2 entry.
Shift Manager Time Date
[2] REVIEW of Reactor Trip Breaker Closure Checkiist is
complete, all surveillance requirements have met their
acceptance criteria, and all open items that affect mode
change have been closed.
Shift Manager Time Date
2.6 Chemistry Sect io n:
NOTE
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.
Chemical Shift Supervisor Time Date
- ------ ----
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
UnitO TO REACTOR CRITICAL Rev. 0026
( Page 77 of 85
Appendix B
(Page 7 of 8)
STARTUP No. Un it _ Date _
3.0 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
co ntinued operatio n in Mode 2.
SM Time Date
[2] ENSURE no open DCN/ECNs that wou ld prohibit a mode
change . (SM concurrence with the Modifications Manager or
des ignee).
SM Time Date
[3] REVIEW all open work activities relative to the unit for the
purpose of iden tifyi ng mainte nance act ivities that could affect
system ope rability prior to mode change
8M Time Date
[4] IF any potential Tech Spec. mode constraint exists ,
THEN
OBTAIN Operations Superintendent reso lution prior to
proceeding with the mode change
8M Time Date
l
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Unit 0 TO REACTOR CRI TICAL Rev. 0026
( Page 78 of 85
Appendix B
(Page 8 of 8)
STARTUP No. Un it _ Date _
3.0 SHIFT MANAGER (SM) HOLD POI NT (continued)
[5] IF th e startup follows a reactor trip or an eme rgency shutdown,
T HEN
A. ENSURE cause of the trip/shutdown has been determined
and will not im pact Mod e 2 entry.
SM Time Date
B. ENSURE Reactor trip report is comp lete.
(O-T I-QXX-OOO-001.0 , Event Critique, Post Trip Report,
_ Equipment Root Cause and Outage Milestone PER
Evaluation)
SM Time Dat e
C. ENSURE O-GO-12 , Realignment of Secondary Equipment
Following Reactor TripfTurbine Trip/Em ergency
shutdown, is comp lete.
SM Time Date
4.0 OPERATIONS SUPERINTENDENT HOLD POINT
Operations Superintendent or his designee con cur s and grant s approval to
proceed to Mode 2, 1.
Operations Superintend ent T ime Date
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
UnitO TO REACTOR CRITICAL Rev. 0026
( Paae 79 of 85
Appendix C
(Page 1 of 1)
DETERMING SOURCE RANGE COUNT RATE DOUBLING
1.0 Calculating Doubling Range
NOTES
1) Source rang e reading shall be allowed to stabilize for approximate ly 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.
Digital indication on shutdown monitor [M-13] is preferred.
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, STA, 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. 0026
( Paqe 80 of 85
Appendix D
(Page 1 of 1)
ACTIONS IF REACTOR STARTUP MUST BE ABORTED
STARTUP No. _ Unit _---..,_ Date _
1.0 Operator Actions
CAUTION
If reactor t rip is required, E-O should be performed inste ad of th is appe ndix.
[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.
Initials Time Date
[4] DETERMINE and CORRECT cause of the discrepancy. o
[5] 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).
[5.2] DILUTE/BORATE in accordance with 0-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] RE-INITIATE 0-GO-2.
End of Document
\.
---- ~--=-=::----------
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Pane 81 of 85
Appe nd ix E
(Page 1 of 2)
ACTIONS IF BANK D RODS REACH FULL OUT POSITION PRIOR TO CRITICALITY
1.0 Operator Actions
NOTE
Allowabl e upper limit for critical posit ion may be above the fully withdrawn position on
Bank D. If Reactor Engineering determines that core response is within acceptable limits,
this app endix 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] PERFORM Appen dix D, Actions if Reactor Startup Must
Be Aborted. D
[2.2] DO NOT CONTINUE this appendi x. D
[3] ENSURE contro l bank 0 inserted to less than or equal to
estimated critical position determined in
0-RT-NUC-000 -003.0 (Startup after refueling)
or 0-SI-NU C-000-001 .0 (Startup afte r non-refueling outage ).
[4] DETERMINE dilution volume to increase core reactivity
by 100 pcm OR as recommended by Rx Engineering.
Rx Engineer
_ _ __ _ gallons
IV
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Paqe 82 of 85
Appendix E
(Page 2 of 2)
STARTUP No. _ Unit _ Date _
1.0 Operator Actions (continued)
CAUTION
NIS indications should be carefully monitored during and following dilution .
[5] PERFORM specified dilutio n USING 0-SO-62-7. o
[6] WHEN at least 30 minutes has elapsed for ReS mixing
AND Rx Engineer concurs with resumin g startup,
TH EN
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 ). o
End of Documen t
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 83 of 85
Source Notes
(Page 1 of 3)
Implementing
Requirements Statement Source Document Statement
Verify MFWP trip bus energized before LER 328 /88-014 C.1
entry into Mode 2.
Revise GOI-2 to require verification of NCO 89011800 2 C.2
intermediate range (IR) status at LER 328/89006
approximately 20 and 25 percent, S53890531 844
verify source range (SR) status and JRB to NRC
channel check at I ~wer power , monitor
core delta Ts at low-power levels and
during power escalation and compare
with NIS response, and verify that the
IR rod stop and trip bistables come in
at the appropriate power level during
power ascens ion.
Following refueling operations SOER-90-003 C.3
relocation of NIS or modifications NCO 900107009
affecting the NIS response , provide NER 1187001
adequate reductions of trip setpoint LER 327/90011 R1
and limitations of reactor power until
accuracy of the NIS is verified. Also ,
provide alternate indications of power
independent of calorimetric
calculations during power ascens ions.
Decommitted 3/12 /99 C.4
Assu rance that TSC computer is reset Verbal commitment to NRC at C.5
prior to startup ; defines "reset" and SNP Meeting 10104/90
"updating". (Modified C.5 permitting
relaxing requirement.)
Provis ions to ensure that enhanced NCO 890097004 C.6
steam generator level recorders are L44 890505 805
( operable in the main control room prior
to entering mode 2.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
( Page 84 of 85
Source Notes
(Page 2 of 3)
Implementing
Requirements Statement Source Document Statement
Based upon the requiremen ts of the PORC Minutes #50880 C.7
May 6, 1991 PORC meeting this 5/06/91T/S 91-08
verification has been added to
implem ent the referenced Technical
Specification chang e for the Core
Operating Limits Report.
Consult Reactor Engineering for NER 89 0794 C.8
guidan ce during evolutions of unusual OER 89 3497
power maneuvers at end of core life.
Provide reactor trip breake r closure U1C5 Outage Critique C.9
checklists to ensure all surveillan ce item
requirem ents for reactor trip breaker
closure are satisfied.
Revise GOI-2 to include a step signoff II S-92-045 C.10
with the TACF review, hold order
review etc. section of GOI , for the Duty
SOS to ensure a board walkdown to
verify proper alignm ent is performed by
a designated SRO prior to mode
change.
Operations startup procedures should: SOER 88-02 C.11
1) Stress conservative actions and NER 88047400
complian ce with written procedures
when repositioning control rods ,
2) Guidance on actions when criticality
will be achieved outside the ECC
toleran ce band ,
3) Avoid activities which dist ract the
operators ,
4) Directions to use pertinent
instrumentation to monitor approach to
criticality ,
5) Periodic pauses during rod
withdrawal.
SQN UNIT STARTUP FROM HOT STANDBY 0-GO-2
Unit 0 TO REACTOR CRITICAL Rev. 0026
(-, Page 85 of 85
Source Notes
(Page 3 of 3)
Implementing
Req ui reme nts Statement So urce Document Statement
Operator Controls and monitoring INPO SOER 94-002 C.12
activities involving possible boron
concentration reduction which could
result in unplanned reactivity changes.
Procedures that do NOT contain TRO I NCO 970071001 C.13
app ropriate verification requirements
will be revised. (This item is NOT
annotated within the procedure, since
the entire procedu re must meet the
verification program requirements .
c.
(
I ~
.--
SQN UNIT STARTUP FROM HOT STANDBY a-GO-2 )
Unit a TO REACTOR CRITICAL Rev. 0025
Page 79 of 85
Appendix C
(Page 1 of 1)
DETERMING SOURCE RANGE COUNT RATE DOUBLING
1.0 Calculating Doubling Range
NOTES
1) Source range reading shall be allowed to stabilize for aporoximately 3 minutes
after each rea ctivity change prior to determining new stable count rate.
2) The highest reading channel should be used when determining stable count rate.
Digital indication on shutdown monitor [M-13] is preferred .
3) Doubling range is used to determ ine 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 IVd by operators, STA, or Rx Engineers.
--
STABLE COUNT RATE DOUBLING RANGE INITIALS
c , COUNT RATE (CR) CR X 1.75 =
(Lower valu e not used
CR X 2.0 = 1st IV
ZD for first doubling) t.f:6 CY-- r;2-
4:0 70 I?O rtL ~
00 13~ IS9 c.. ~
I S~ 2 7f ]('( 2- <>::
3 1~ 5'50 4?3) 2- {.--
(j3 5 I {( ( /270 ~ ~
(2- 7 D 2 Z2-7.---- 2 SZiO W'---- ur-
End of Section
SON ESTIMATED CRITICAL CONDITIONS 0-SI -NUC-000-001 .0
c 0 Rev 5"::::::::-
Page 35 of 42
APPENDIXC
Page 8 of 10
MONITORING THE APPROACH TO CRITICALITY
DATA SHEET C-1
ICRR DURING ROD WITHD RAWAL FOR CHANNEL N-32
UNIT \ CYCLE DATE ,...-ro Oo')'
ECC:- -'PPM \.5"~ STEPS T
.
. I
I
I "'.
,l," ' I
I
: :
..
: :
"
: :
e
: :
: : : :
: : :
"
: : : :
'A
: :
: : :
o : :
:
"
'"
,,,
"'I . "'I ...
COUNT SECS Cr; BANK STEPS ICRR INITIALS
CRO iq - 1.00 /"-"
CR 1 3 '1 .'1if r-/
CR2 7 "\' ;Z-L/ A/
CR3 /,5 . ,,1- .........
CR4
CR5
-';o g' _
6 / '<;'
, t lo
. u) ---
"--
-../'
CR6 12.7U . ciS
CR7
CR8
CR9
REVIEWED BY - -- -=:-:-::=-=-=0-==-- - DATE _
REACTOR ENGR
( l
( TENNESSEE VALLEY AUTHOR ITY
SEQUOYAH NUCLEAR PLANT
SYSTEM OPERATING INSTRUCTION
0-50-85-1
CONTROL ROD DRIVE SYSTEM
Revision 32
QUALITY RELATED
PREPARED BY: JENNIFER REGAN
RESPONSIBLE ORGANIZATION: OPERATIONS
APPROVED BY: W. T. LEARY
EFFECTIVE DATE: 1211112006
LEVEL OF USE: CONTINUOUS USE
REVISION
DESCRIPTION: Revised to incorporate the new reactor breaker close control switch,
2-HS-99-7, per DCN D21843A.
PERFORMANCE OF THIS PROCEDURE COULD IMPACT REACTIVITY
l
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 PREREQtJlSITE ACTIONS 9
5.0 STARTUP/STANDBYREADINESS................................................................. 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 ReseUClose 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
Sect ion Title Page
8.0 INFREQUENT OPERATION . 56
8. 1 Alternate Method of Paralleling MG Set A .. 56
8.2 Alt ern ate Method of Paralleling MG Set B .. 58
8.3 Resetting Step Counters After Withdrawing Rods Above 23 1 Steps .. 60
8.4 Resetting Step Counters After Inserting Rods Below 0 Steps .. 61
8.5 Placin g MG Set A In Service for Maintenance .. 62
8.6 Placin g MG Set B In Service for Mainte nance .. 69
9.0 RECORDS . 76
SOURCE NOTES 77
ATTACHMENTS
ATTACHMENT 1: CONTROL ROD DRIVE SYSTEM
POWER CHECKLIST 1-85-1 .01
ATTACHMENT 2: CONTROL ROD DRIVE SYSTEM
POWER CHECKLIST 2-85-1.01
(
--- --------- ---------
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
c 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 instru ction 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
c
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1.2 Rev 32
( Page 6 of??
3.0 PRECAUTIONS AND LIMITATIONS
A. Rod thermal lock-up is NOT a concern when the reactor trip breakers are
OPEN. If reactor trip breakers are CLOSED and an RCS cooldown of
greater than 50°F is planned , the shutdown and control banks should be
withdrawn at least 5 steps each . This will limit the possibility of "thermal lock-
up" of the rods. This does not apply if performing sections 8.5 or 8.6.
B. If both MG sets are to be shutdown, the control rods and shutdown rods shall
be insert ed 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 Contact s could
resu lt 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 withd rawal 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 Controi 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 withdra wing 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
c 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 100 psig.
L. RPl s 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
TE MPERATURE
" 190°F 10 minutes ON 20 minutes OFF
" 200°F 6 minutes ON 24 minutes OFF
Tim e limitations are due to a lower air flow rate of 48 ,000 cfm across the
shroud combined with a higher temperature (Reference TSIR-97-BOP-30-636
and We stinghouse Letters RIM's #B38931005806, B38930920800, and
8 38931 005803).
N. The following failures will render the rod control system incapable of
automatic and / or manual motion without any annunciation or indicatio n:
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 chan nel may cause step change in
input to rod control. A delay of at least 3 minutes prior to returning rod control
to auto matic will allow lead/lag signal to decay off.
SON CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 8 of 77
3.0 PRECAUTIONS AND LIMITATIONS (Continued)
P. Directiona l Overcurrent Relay Targ ets are reset by depressing the Relay
Target Reset Pushbutton on the panel to break the target coil seal in circuit
and th en lifting the mechanical reset at the bottom of the relay cover.
Q. US I SRO Oversight for control rod manipulation shall include :
1. Prior to Rod Movement
a. Ensure RPI's within T.S. range (+ or - 12 steps)
b. Ensure delta flux will not be adversely affected
c. Ensure Ta vg and Rx Thermal power will not be adversely affected
d. Verify on target with Rx Eng reactivity balance sheet
e. Verify power chan ge will not exceed hourly rate
f. Ensure no simultaneous reactivity manipulations in progres s
(Le.: borations, dilutions or turbine load change s)
2. During Rod Movement
a. Ensure RO has peer check
b. Ensure RO is following procedu re
c. Ensure RO under stands 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 audib le
indication of rod step
f. Ensure peer check is doing their job
g. Re-verify steps a - d of initial evalua tion
h. Ensure procedure is follo wed placing rods back to auto
(Tavg - Tref mismatch)
L Monitor plant for expected response
---====----"==~ .== = = =='----._----
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
(' 1,2 Rev 32
Page 39 of 77
Unit ( Date 'tH~
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
<190°F 10 minutes ON 20 minutes OFF
<200°F 6 minutes ON 24 minutes OFF
[1] ENSURE Section 5.2, Reset/Close Reactor Trip
Breakers has been compieted.
[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. ,Itt. 1MM5-
1st cv
NOTE 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.
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. [3] MOMENTARILY PLACE [SUS], Rod Control Startup
Step Counter Reset to the STARTUP position to reset
Control Rod Drive System.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 40 of 77
Unit Date J1l/)"'1
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*55-4B] using
[XS-55-4A] , Annunciator RESET/ACKITEST Switch.
[8] VERIFY the following rod control system alarms on panel
[XA-55-4B] are NOT LIT:
WINDOW NOT LIT
NUMBER N)
5 (A5) IB'
6 (A6) ~
11 (B4) IE"'
12 (B5) 10"
13(B6) iW
18 (C4) Il:i1
19(C5) ~
27 (06) &r
34 (E6) 1!6
11/
(
SQN CONTROL ROD DRIVE SYSTEM 0-50-85-1
1,2 Rev 32
( Page 41 of 77
Unit I Date 110"1
6.3 Manual Operation of Rod Control System Below 15 Percent Power
(Contin ued )
[9] ENSURE Plan t computer points for rod ban k position are
ZERO using th e following computer points :
COMPUTER PT ROD BANK -,J
U0049 Control A [JJ'"
U0050 Con trol B lit"
U0051 Control C Ii;1(
U0052 Control D [B'"
U0053 Shutdown A I!2f
U0054 Sh utdown B IB'"
U0055 Shutdown C IB"
~
- U0056 Shutd own D
[10] MONITOR Control Rod position USING Rod Position Indicators
ICS screen 30 minute trend during SD & Control Ban ks
with drawal to aid in det ectin g rod misalignm ent.
[11] IF Individual Rod Pos ition Indicatio n does not indicat e proper rod
po sition d uring withdraw al of SD Ban ks , THEN
[a] STOP rod withdrawa l. f.Zi f?
[b] ENSURE subcriticality. k!jJ:J
[e] CONTACT MIG
AND
INITIATE troubleshooting. I!jlt
[d] IF troubleshooting does not resolve the problem ,
OR
sub criticality can NOT be verifie d ,
THEN
INITIATE Rea ctor TRIP . iliff
[12] IF Individual Rod Position Indication does not ind icate pro per rod
po sition during withdraw al of Control Ban ks , THEN
GO TO AOP-C.01 se ction 2.6 Rod Pos ition Indicator (RPI)
Malfunction - Modes 1 or 2. ~A
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 42 of 77
Unit. (
-'- _ Date TIJ0'1
6.3 Manual Ope ration of Rod Cont rol System Below 15 Percent Powe r
(Continued)
CAUTION Unde r normal co nditions control rod banks mus t be withdrawn
and inserted in t he prescribed sequence. For w ithdrawal, the
sequence is Shutdown Bank A, Shutdown Bank B, Shutdown
Bank C, Shutdown Bank D, Control Bank A, Control Bank B,
Control Bank C, Control Bank D. The insertion sequence is the
reve rse of the withdrawal seq uence.
NOTE 1 Startup rate, Source range, Intermediat e 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] PLA CE [HS*S5-51101, Rod Control Mode Selector to the
SBA position. 1lL 1 ~
1st CV
[14] VERIFY Rod Speed Indicator [SI-412]. indicates
64 Steps/minute. 1!I£. / ~
1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 43 of 77
Unit --:(___ Da te-L=~_
6.3 Manual Operation of Rod Control System Below 15 Percent Powe r
(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-85-5111] , Rod Control Switch to withdraw Shutdown Bank A
one-half step at a time, for one full step.
~ I /11M(
1st cv
[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.
JJ1L /~
1st CV
[d] VERIFY group demand position counters advance properly.
[e] IF group demand position counters do NOT advance properly,
THEN
A. STOP rod withdrawal. .Q2>>.
B. INITIATE WO to have counter repaired. fi[1r
C. WHEN counter is repaired , THEN
1. ENSURE Shutdown Bank A fully INSERTED. ~
2. RETURN to beginning of this step. ,fjd-
NOTE The fully withdrawn position for shutdown and
control rods is defined by TI-28, Atl. 6.
[16] WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN
position using [HS-85-5111] . ~ /IIIW
1st CV
(
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 44 of 77
Unit. 1 Date'--L"""'"tDJ-_
6.3 Manual Operation of Rod Control System Below 15 Percent Power
(Continued)
[17] PLACE IHS-85-5110], Rod Control Mode Selector to the
SBB position. ,( /t( I /UW{
1st CV
[18] VERIFY Rod Speed Indicator [51-412], indicates
64 Steps/minute.
NOTE The following failures will render the rod control syste m incapable
of automatic and / or manu al 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 co unte rs
o pera tional by perf orming the followin g: [C.2]
[a] BUMP [HS-85 -5111], Rod Control Switch to withdraw Shutdown Bank B
one-ha lf step at a time , for one full step .
.iJtL I AlI'i.
1st cv
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-5111] to withdraw Shutdown Bank B
one -ha lf step at a time , for the second full step .
d If!- I 1I'fJ-'i
1st cv
[d] VERIFY group demand position cou nters advance properly .
[e] IF g roup demand pos ition counters do NOT advance properly,
THEN
A. STOP rod withdrawa l.
B. INITIATE W O to have counter repaired .
C. WHEN counte r is repaired, THEN
1. ENSURE Shutdown Bank B fully INSERTED and
2. RETURN to beginning of this ste p.
[20] WITHDRAW Shutdown Bank B to the FULLY WITHDRAWN
position usi ng [HS-85-5111] . ~ /~
1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 45 of 77
Unit. --'-{___ Date--l.-=-""=f-_
6.3 Manual Operation of Rod Control System Below 15 Percent Power
(Continued)
[21] PLACE [HS-85-5110], Rod Control Mode Selector to the
SBC position. ~ I MfI"l.
1st CV
[22] VERIFY Rod Speed Indicator [SI-412], indicates
o Steps/minute . AJ.<, /~
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. !JtL I MJVI..
1st CV
[b] CHECK group demand position counter advances properly.
[c] BUMP [HS-85-5111] to withdraw Shutdown Bank C
a second full step. "-It<
1st
I ~
CV
[d] VERIFY group demand position counter advanced properly.
tel IF group demand position counters do NOT advance properly,
THEN
A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired , THEN
1. ENSURE Shutdown Bank C fully INSERTED and
2. RETURN to beginning of this step .
[24] WITHDRAW Shutdown Bank C to the FULLY WITHDRAWN
position using [HS-85-5111]. ;flf( I MWJ2
1st CV
(
SQN CONTROL ROD DRIVE SYSTE M 0-SO-85-1
c 1,2 Rev 32
Page 46 of ??
Unit I Date 7Tf{Jtry
6.3 Manual Operation of Rod Control System Below 15 Percent Power
(Continued)
[25] PLACE [HS-85-511 OJ, Rod Control Mode Selector to the
SBD position. .llt..i- I 111M
1st CV
[26] VERIFY Rod Speed Indicato r [SI-412] , indicates
o Steps/minute. I't /I<. I ...!J!..1!!l
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 0 demand position counters
operational by performing the following: [C.2]
[a] BUMP [HS-85-511 1] , Rod Control Switch to withdraw
Shutdown Bank 0 one full step. J!.l!:S..- I ~
1st CV
[b] CHECK group demand position counter advan ces properly.
[c ] BUMP [HS-85-5111] to withdraw Shutdown Bank 0
a seco nd full step. ~ l tHJIL
1st CV
[d] VERIFY group demand position counter advanced properly.
[e] IF group demand position counters do NOT advance properly,
THEN
A. STOP rod withdrawal.
B. INITIATE WO to have counte r repai red.
C. WHEN counter is repaired, THEN
1. ENSURE Shutdown Bank 0 fully INSERTED and
2. RETURN to beginning of this step.
[28] WITHDRAW Shutdown Bank D to the FULLY WITHDRAWN
posi tion using [HS-85-5111]. I!ft
1st
I AI
CV
W '
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 47 of 77
Unit ) Date !7If'1
6.3 Manu al 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-OOO-003.0.
[29] PLACE [HS-85-5110], Rod Control Mode Selector to the
MANUAL position. Jl/f( , AIM.
1st cv
[30] VERIFY Rod Speed Indicator [SI-412] , indicates
48 Steps/minute. 11 #<. , Awl
t st 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. !1J.ti.. IAtr
l si CV
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-5111] to withdraw Control Bank A
one-half step at a time, for the second full step. AIIf.. , ~
1st CV
[d] VERIFY group demand position counters advance properly. QV
tel IF group demand position counters do NOT advance properly,
THEN
A. STOP rod withdrawal. ~
B. INITIATE WO to have counter repaired. f/'P-
C. WHEN counter is repaired, THEN
1. ENSURE Control Bank A fully INSERTED and Af1J}
2. RETURN to beginning of this step. ~
saN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 48 of 77
Unit ( Date 1vl?o9-!p
6.3 Manual Operation of Rod Control System Below 15 Percent Power
(Continued)
[32] CONTINUE withdrawal of Control Bank A using [HS-85-5111] , IJ lL(
Rod Control Switch to 128 steps or next doubling. "'F,
NOTE When Control Bank A is above 20 steps. alarm FULL
LENGTH RODS AT BOnOM 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 BOnOM alarm on panel [XA-55-4B]
CLEARS.
SQN CONTROL ROD DRIVE SYSTEM 0-50-85-1
1,2 Rev 32
( Page 49 of 77
Unit I Date iWA-y
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-85-5111J, Rod Control Switch to withdraw
Control Bank B one-half step at a time, for one full step. "#1st
f AW t..
cv
[b] - CHECK group demand position counters advance properly.
[e] BUMP [HS-85-5111] to withdraw Control Bank B
one-half step at a time, for the second full step. .!:!I:L f M CI't
t st cv
[d] VERIFY group demand position counters advance properly.
[e] IF group demand position counters do NOT advance properly ,
THEN
A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
1. ENSURE Control Bank B fully INSERTED and
2. RETURN to beginning of this step.
[35] CONTINUE withdrawal of Control Bank Busing [HS-85-5111]
to 128 steps or next doubling .
c.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 50 of 77
Unit { Da~ WR~
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 demand position counters
operational by performing the following: [C.2]
[a] BUMP [HS-85-5111] , Rod Control Switch to withdraw
Control Bank C one-half step at a time , for one full step. t1.JfL , IIJ-ld-
1st CV
[b] CHE CK group demand position counters advance properl y.
[c] BUMP [HS-85-5111] to withdraw Control Bank C
one-half step at a time, for the second full step. m , cvMWI-
1st
[d] _ VERIFY group demand position counters advan ce properl y.
[e] IF group demand position counters do NOT advance properly,
THEN
A. STOP rod withdrawal. R)f
B. INITIATE WO to have counter repaired. ~
C. WHEN counter is repaired , THEN
1. ENSURE Control Bank C fully INSERTED and ~
2. RETURN to beginning of this step. ~
[37] CONTINUE wit hdrawal of Control Bank C using [HS-85-5111]
to 128 steps or next doubling. I. It {
NOTE Three steps are added to the low-lo w insertion limit (110
steps @ zero power) until LEFM is availabl e.
[38] WHEN Control Bank C is '" 113 Steps, THEN
ENSURE Window 14 (B-7), ROD CONTROL BANKS
LIMIT LOW-LOW alarm on panel [XA-55-4B]
CLEARS. LIf(
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1
1,2 Rev 32
( Page 51 of 77
Unit I Date ]uO""1
6.3 Manual Operation of Rod Con tro l System Below 15 Perce nt 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 is '" 123 steps. THEN
ENSURE Window 7 (A-7). ROD CONTROL BANKS
LIMIT LOW alarm on panel [XA-55-4B] CLEARS .
[40] WHEN Control Bank C is withdrawn to 128 steps. THEN
ENSURE Control Bank D demand position counters
operational by performing the following: [C.2]
[a] BUMP [HS-85-5111] . Rod Control Switch to withdraw
- Control Bank D one-half step at a time, for one full step. JlIf( I NtJil.
1st cv
[b] CHECK group demand position counters advance properly. [i}
[c] BUMP [HS-85-5111] to withdraw Control Bank D
one-half step at a time, for the second full step. ~ I /J(if/.
1st CV
[d] VERIFY group demand position counters advance properly. [)"
[e] IF group demand position counters do NOT advance properly.
THEN
A. STOP rod withdrawal. i!1.4
B. INITIATE WO to have counter repaired. If/JI
C. WHEN counter is repaired, THEN
1. ENSURE Control Bank D fully INSERTED and ~
2. RETURN to beginning of this step. ~
[41] CONTINUE withdrawal of Control Bank D using [HS-85 -5111]
to next doubli ng or criticality.
End of Section 6.3
l
ROD CONTROL SYSTEM MALFUNCTIONS AOP-C.01
SQN
Rev. 16
(
I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
2.1 Continuous Rod Bank Movement
1. CHECK rod control:
a. ENSURE rod control in MAN.
b. CHECK rod motion STOPPED. b. TRIP the reactor, and
GO TO E-O, Reactor Trip or Safety
Injection.
--~.--
CAUTION: - Control Rods should NOT be manually withdrawn during a plant
transient.
2. CHECK for steam line or feedwater line
break:
a. CHECK for rising reactor power a. GO TO Step 3 .
with dropping T- avg .
b. GO TO AOP-S.05 , Steam Line or
Feedwater Line Break/Leak.
--~.--
(
Page 5 of 62
JPM B.1 .b
Page 1 of 14
Rev. 11
SEQUOVAHNUCLEARPLANT
( JOB PERFORMANCE MEASURE
B.1.b JPM 77-2AP
Perform DIG Load Test on 1B-B DIG
(with low oil press)
(
PREPAREDI
REVISED BY: Date/
VALIDATED BY: * Datel
APPROVED BY: Datel
(Operations Training Manager)
CONCURRED: ** Date/
(Operations Repres entative)
* 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 14
Rev. 11
NUCL EAR TRAININ G
REV IS ION/U SAGE LOG
R EVISION DESCRIPT ION OF V DATE PAGES PREPARED/
NUMBER REV ISION AFFECTED REVISED BY:
7 Revised to reflect revision changes in SI- N 10/14/99 All SR TAYLOR
7B, changed critical steps for consistency
with JPM 77-5AP reviewed/approved
4/20/99, corrected typos and incorporated
comments from 1999 cycle 5 requal
perfo rmances of JPM 77-2AP. Flow of
the J PM is not affected .
penlink Deleted step 20 based on rev 20 of O-AR* N 8/9/00 5,12 SR Taylor
M26-B , Updated rev level
penli nk SO-82 rev update only N 8/17/00 4 SR Tay lor
penlin k 0-AR-M26-B rev chg only N 8/28/00 4 SR Taylor
penli nk 0-SI-OPS-082-007.B rev chg only N 6/21/01 4 W R Ramsey
pen/in k 1-SI-O PS-082-007.B rev 25 Update minor N 09/07/01 ALL WR Ram sey
chang es related to stopwatch usage
( 8 Incorporated pen/ink changes ; updated to
recent revisions of references; no impact
N 8/20/02 All J P Kearney
on JPM flow
9 Revised remote funct ions used to conform N 12/0 1/2003 4,8, 10 JJ Tricoglou
to new simutator configuration
10 Updated to curre nt revisions and IC. N 8/11/04 All MG Croteau
11 Updated to current revisions . Minor format N 01/3 1/07 All RH Evans
chan ges
v - Specify if the J PM change will require another validation (Y or N).
See cover sheet for criteria.
(,
JPM B.1.b
Page 3 of 14
Rev. 11
SEQUOYAH NUCLEAR PLANT
ROISRO
JOB PERFORMANCE MEASURE
(
Task:
Perform DIG Load Test on 18-B DIG
JAITA tas k # :
0640020101 0640040101 0640060101 (RO)
KIA Rati ngs:
064A4.01 (4 .0/4.3) 064A1.01 (2.0/3.1)
064A4.02 (3.3/3.4) 064A4.03 (3.213.3)
064A2.09 (3.1/3.3) 064A3.06 (3.3/3.4)
Task Stand ard :
Perform DIG Operability Test per 1-SI-OPS-082-007.B. specifically manually start the DIG. Open
alternate ERCW supply valve and emergency stop DIG on low oil pressure annunciator.
Eva luation Method : Simulator _ -!:
X,--_ In-Plant _
============== =========================== ==================================== ======
Performer:
NAME Start Time
( Performance Rating: SAT UNSAT Performance Time Finish Time
Evaluato r: I
SIGNATURE DATE
====================================================================================
COMMENTS
('
JPM B.1.b
Page 4 of 14
Rev. 11
SPECIAL INSTRUCTIONS TO EVALUATOR :
1. Sequenced steps identified by an "s"
( 2. Any UNSAT requires comments
3. Acknowledge any associated alarms.
4. Initialize Simulator to IC-16.
5. A Console operator will be required to enter overrides and play role of AUO on Radio.
6. When operator starts step #19, insert IMF AN_OV_946 f :2.
7. An extra simulator operator will be needed at step 5 for timing the D/G.
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 13 minutes Local _
Tools/Equipment/P rocedures Needed :
Marked up portions of 1-SI*OPS-082-007.B:
* Section 4;
* Section 6.1; and,
* Appendix "C".
O-AR-M26-B window B-4
References'
Reference Tille Rev No.
1. 1-SI-OPS-082-007.B Electrical Power System Diesel Generator 1B-B 39
2. O-AR-M26-B Annunciator O-XA-55-26B 27
(
JPM B.1.b
Page 5 of 14
Rev. 11
(
================= ======== =====================================================
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. Whe n you comp lete the task successfully, the objective for this job performance measure
will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate
that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
1. Both units are at 100% RTP.
2. All systems are OPERABLE, except for the 1B-B DIG , 0-GO -16 has been completed on all the A train
equ ipment.
3. Maintenance has been completed on the 1B-B DIG and the clearance has been removed.
4. The DIG has been rolled and is in standby alignment using 0-SO-82-2.
5. The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082 *007.B and all parameters
are within limits.
6. The U1 Control Room AUO has verified breaker 1934 is removed.
7. SI-166.36 is NOT required.
( 8.
9.
D/G-DAQ has been installed.
Room fire protection is in service.
10. Sect ion 4.0 of 1-SI-OPS-082-007.B is complete.
INITIATING CUES :
1. The U1 US/SRO has reviewed the comple ted work package for the 1B-B DIG , all that remains is to
perform 1-SI-OPS-082-007 .B for the PMT.
2. You are an extra unit operator and have been assigned to perform the operability run of DIG 1B-B per
SI-OPS-08 2-007 .B.
1. T he PMT requires the AMB IENT MANUAL START method for testing.
3. Notify the US when the test is comp lete.
JPM B.1.b
Page 6 of 14
Rev. 11
Job Pertormance Checklist:
STEP/STANDARD SATIUNSAT
( STEP 1.: Operator obtains a copy of the appropriate procedure. - SAT
NOTE: Initial conditions cover steps up to transition to App "C" . - UNSAT
STANDARD: Operator obtains a copy of 1-SI-OPS*082-007.B. Pertormance of task Start T ime- -
will start with AppendiX C.
COMMENTS:
STEP 2.: [1) ENSURE [D-HS*82-48) . 1B-B D/G mode selector switch in the UNIT - SAT
position.
- UNSAT
STANDARD : O-HS-82-48 in UNIT position on O-M-26. Green light ON.
COMMENTS:
STEP 3.: [2) Place [1*HS*57*74). D/G 1B-B Synchronize Switch in the SYN position. - SAT
NOTE: O*EI*82*35 and O*XI*82*33 will indicate running voltage & frequency. - UNSAT
( STANDARD: 1-HS-57-74 in "SYN" position on O-M-26. This step is cr itical to allow
to allow DIG to be synchronized to the Shutdown Bd. Critical Step COMMENTS:
(
JPM B.1.b
Page 7 of 14
Rev. 11
Job Performance Checklist:
STEPISTANDARD SAT/UNSAT
( STEP 4. [3] PERFORM the following to initiate the DIG start signal: - SAT
[a] IF the D/G-DAQ is to be used, THEN NOTIFY D/G-DAQ - UNSAT
Operator to
START the D/G -DAQ
NOTE: Operator should coo rd inate t he start of the D/G-DA Q just prior to
DIG st art actu ation.
Cue Console operator Play ro le o f DIG-DAQ operator: DI G-DAQ
computer is running.
STANDARD: Operator notifies the DIG-DAQ operator to start the DIG-DAQ.
COMMENTS:
STEP 5.: [b] PROCEED with the countdown: 3,2,1, START. - SAT
[c] DEPRESS [0-HS-82-46A] . DG 1B-B Emergency Start Switch - UNSAT
AND START stopwatch.
c [d] WHEN voltage >6800 volts AND frequency >58.8 Hz, THEN
STOP stopwatch.
Critical Step
CUE: An ext ra ope rato r with stop wat ch is sta nding by .
STANDARD : D-HS-82-46A mo me ntaril y depr essed . Green light will go "out" and
red li ght will com e "on" abo ve DIG mimic. [Not critical: DIG running
aiarm will ANN to indicate DIG> 40 rpm. Incoming voltage and
frequency are verified on 0-EI-82-34 and 0-XI-82-32. Portions of this
step is crit ical to start t he DIG.
COMMENTS:
STEP 6.: [4] ENSURE [1-FCV-67-67] , ERCW cooling water supply valve is OPEN. - SAT
- UNSAT
STANDA RD: ERCW valve 1-FCV-67-67 is verified open.
COMMENTS:
JPM B.1.b
Page 8 of 14
Rev. 11
Job Performance Checklist:
STEPISTANDARD SAT/UNSAT
( ST EP 7.: [5] RECORD the steady state values for the following: - SAT
A. [O-EI-82-34] . DG 1B-B incoming Voltage.
B. rO-XI-82-321, DG 1B-B incoming Frequency. - UNSAT
C. Time from Stopwatch (es):
Seco nds Stopw atch ID Number
Seconds Stopwatch 10 Number
CUE: Time from s top wat ch . = 9.48 seconds
STANDARD: Operator records parameters as directed and verifies acceptance criteria
met. DIG voltage (as indicated on INC Voltage Gen 1B-B 0-EI-34) is;::
6800 but :s. 7260 volts and freq uency (as indicated on INC Freq Gen 1B-B
0-XI-82-32) is ;:: 58.8 Hz and s 61.2 Hz
COMMENTS:
ACCEPTANCE CRITERIA: DIG 1B-B achieves steady state generator voltage of ;::6800 and ~7260 volts and
frequency of ;::58.8 Hz and :s. 61.2 Hz.
( STEP 8.: [6] RECORD Voltage Regul ator Control Current. - SAT
Cue: Voltage Regulator Control Current Is 1.8 dc amps. - UNSAT
STAN DAR D: Operator records Voltage Regulator Control Current.
COMM ENTS :
ACCEPTANCE CRITERIA: Voltage Regulator Control Curren t between 1.0 - 2.5 dc amps. The Voltage
regulator card must be functioning properly to conside r DG operable.
STEP 9.: [7] ENSURE DIG 1B*B [86 LOR] red light NOT ILLUMINATED, at DIG local - SAT
relay panel.
- UNSAT
Cue: Role Playas DIG operator - 86 LOR local red light Is not
Illuminated.
STANDARD Operator request DIG operator to verify red light on 86 LOR at DIG is not
illuminated.
COMMENTS:
JPM B.1.b
Page 9 of 14
Rev. 11
Job Performance Checklist:
STEP/STANDARD SATIUNSAT
( Booth operator: to reset 86LOR, IRF EGR08 f:1 ;
then notify operator 86 LOR Is reset.
NOTE Do not hold [86 LOR] in RESET position if it does not latch on the first
attempt. Coil failure may result if relay is held in RESET position.
STEP 10.: [8] RESET [86 LOR] Lockout Relay. on DIG local relay panel. - SAT
NOTE: When requested of DIG AUO. reset 86LOR - UNSAT
[Booth operator: IRF EGR08 f:1 to reset 86LOR ;
then no tify operator 86 LOR is reset)
Critical Step
STANDARD: 86 LOR is reset. This step is critical to allow paralleling the D/G to
the Shutdown Bd.
COMMENT S:
STEP 11.: [9] VERIFY [86LOR] is reset by amber light [0-XI-82-49] ILLUMINATED on
0-M-26.
STANDARD: 86 LOR amber light on 0-M-26 is verified lit
( COMMENTS:
STEP 12.: [10] IF the D/G-DAQ was used. THEN - SAT
RECORD from the time required to achieve :2: 6800 Volts and z 58.8 HZ - UNSAT
from the D/G*DAQ computer:
Seconds
Cue: Time was 9.5 seconds for D/G*DAQ.
STANDARD: Operator ensures the DG accelerates to at least 900 rpm (58.8 - 61.2 Hz)
and Voltage and frequency are within limit within the required 10
seconds. (Evaluator can sign for Tech Support)
COMMENTS:
(
JPM B.l.b
Page 10 of 14
Rev. 11
Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
c ACCEPTANCE CRITERIA: D/G lB-B start from ambient condition achieves in less than or equal to 10
seconds generator voltage 2: 58.8 Hz.
STEP 13.: [11] RECORD start as ambient in 0-SI*OPS-082-007 .M. - SAT
Cue: Another operato r w ill recor d st art. - UNSAT
STANDARD: Operator logs (addresses logging) the start in 0*SI-OPS-082-007.M.
COMMENTS :
ST EP 14.: [12] RETURN to Section 6.1, Step [9] of this instruction. - SAT
STANDARD: Operator returns to the appropriate section and step of the procedure. - UNSAT
(Exits Appendix C)
COMMENTS:
EVALU ATOR NOTE: Followina steps evaluate procedure section 6.1.
( STEP 15.: [9] PERFORM the following to wipe the Automatic Voltage Control Rheostat: - SAT
[a] RECORD voltage from [D-EI-82-34]. - UNSAT
[b] ENSURE [O-HS-82-42] DG lA-A Voltage Regulator Switch in the
PULL-P-AUTO position
[c] DECREASE voltage to 6700 volts on [O-EI-82-34) USING [D-HS-
82-42]
[d] INCREASE voltage to 7300 volts on [O-EI-82-34] USING [O-HS-
82-42]
[e] RETURN voltage to value recorded in [9Ile].
STANDAR D: Operator uses 0-HS-82-42 to decrease voltage to 6700 volts and
increase voltage to 7300 volts, then return voltage to the value recorded
in step [glle].
COMMENTS:
(
JP M B.1.b
Page 11 of 14
Rev. 11
Job Perform ance Checklist:
STEPISTANDARD SAT/UNSAT
( STEP 16.: [10] PLACE [D-HS-82-48] , Mode Selector Switch in PARALLEL position. - SAT
- UNSAT
STANDARD: 0-HS*82-48 rotated to the PARALLEL position. Red light "on" & green
light "off". This step is critical to place speed droop circuit in Critical Step
service.
COMM ENTS:
STE P 17.: [11] ADJUST [0-HS-82-431. DG 1B-B Speed Control Switch to obtain a - SAT
synchroscope indication of slowly rotating in [FAST] direction.
- UNSAT
STANDARD : Operator adjusts speed control hand switch 0-HS-82-43 such that
synchrosco pe (XI-82-31) is moving slowly in the fast direction (slowly
clockwise) .
COMM ENTS:
STEP 18.: [12] ENSURE [0-HS-82-42] . DG 1B-B Voltage Regulator Low-Raise Switch in - SAT
( the PULL-P-AUTO position. AND
- UNSAT
ADJUST to match incoming voltage with running voltage.
STANDARD : Operator ensures HS-82-42 in PULL-P-AUTO and adjusts DIG voltage Critical Step
such that incoming voltage (EI-82-34) and running voltage (EI-82-35)
are approximately equal. Only the bold portion of t hi s standard is
critical.
This is critical to match voltage of the DIG w ith the voltage on the
Shutdown Bd.
COMMENTS:
JPM B.l .b
Page 12 of 14
Rev. 11
Job Performance Checklist:
STEP/STANDARD SAT/UNSAT
( Booth operator: INSERT the following IMF AN_OV_946 1:2 when operator begins
discussing the step to close DIG Bkr.
STEP 19.: [13] WHEN the synchroscope DG 1B-B [o-SI-82-31] indicates 12 O'Clock - SAT
position, THEN
CLOSE breaker [1914] via [l -HS-57-73Aj, 1914 DG lB-B to SO - UNSAT
BD lB-B, AND
START stopwatch.
NOTE: Whe n operator begins disc ussing t he step to close DIG Bkr, insert
override IMF AN_OV_946 f:2 .
STANDA RD: Operator discusses closing DIG 1B*B breaker 191 4, but should stop due
to annunciator.
COMMENTS:
STEP 20.: Respond to annuciator panel 0-M-26B window B-4. - SAT
STANDARD: Operator pulls AR 0-M26-B and consults page for window B-4 or TAKES - UNSAT
PRUDENT ACTION TO EMERGENCY STOP DIG.
( COMMENTS :
EVALUATOR NOTE: The next Performance Step is from the ARP Corrective Actions.
STEP 21.: [1] IF DIG running with no valid accident (blackout or SI) signal present, - SAT
THEN,
ENSURE DIG shutdown by depressing emergency stop pushbutton 0- - UNSAT
HS-82-47A.
Cue: If contacted, EDG AUO reports Engine 1 LO Pressure is 15 psig and
decreasing. Critical Step
STANDARD: Oper ato r init iates action [w ithin 2 mi nutes] after determining no valid
accident signal, lube oil pressure low by depressing emergency stop
button for Diesel Generator 1B-B.
This step is critical to prevent damage to th e D/G due to low lube oil
pressure.
COMMENTS:
JPM B.1.b
Page 13 of 14
Rev. 11
Job Performance Checkl ist:
STEP/STANDARD SAT/UNSAT
c STEP 22.: Inform US/SRO of Emergency stop of Diesel Generator 1B-B. SAT
US/SRO instructs opera tor to standby for further instructions. UNSAT STANDARD : Operator informs US/SRO of Emergency stop of Diesel Generator 1B-B. COMMENTS : Stop T ime__
FROM : SEQU[ YRH OPERRTOR TRR INING PHONE NO. 423 843 4339 '"pr. 04 2007 02 : OOPM P4
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 understa nd your assigned
task. To indicate that you have completed your assigned task return the handout
sheet I provided you.
INITI,~L CONDITIONS:
Both units are at 100% RTP.
All systems are OPERABLE, except for the 1B-B DIG , 0-GO-16 has been completed on
all the A train equipment.
Mainten ance has been completed on the 1B-B DIG and the clearance has been
removed .
The DIG has-been rolled and Is in standby alignment using 0-80-82-2.
The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082-007.B and all
parameters are within limits.
The Ul Contro l Room AUO has verified breaker 1934 is removed.
SI-166 .36 is NOT required.
D/G-DAQ has been Installed.
Room fire protection is in service.
Section 4.0 of 1-SI-OPS-082-007.B is complete.
INITIATING CUES:
The U1 US/SRO has reviewed the completed work package for the 18-8 DIG, all .
that remains is to perform 1-SI-OPS-082-007.B for the PMT.
You are an extra unit operator and have been assigned to perform the operability.
run of DIG 1B-B per SI-OPS-082-o07.B.
The PMT requires the AMBIENT MANUAL START method for testing.
Notify the US when the test is complete.
CANDIDATE CUE SHEET
(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will ex plain the initial co nditio ns, and state th e task to be performed . All control
roo m steps sh all be perform ed for this JP M , including any require d
comm un ications. I will prov ide init iatin g cues and reports on other actions when
directed by you. Ensure you indicate to me when you understand your assigned
tas k. To indicate that you have compl eted your assigned task return the handout
sh eet I provided you .
INITIAL CONDITIONS:
Both units are at 100% RTP.
All systems are OPERABLE, except for the 1B-B DIG , 0-GO-1 6 has been completed on all the
A train equipment.
Maintenance has been completed on the 1B-B DIG and the clearance has been removed.
The DIG has been rolled and is in standby alignment using 0-SO-82-2.
The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082-007.B and all
parameters are- within limits.
The U1 Control Room AUO has verified breaker 1934 is in the Disconnect position.
SI-166.36 is NOT required.
D/G-DAQ has been installed.
Applicable steps of Appendix J, Monitoring the DIG Starting Air System, compl
Room fire protection is in service. l'.
Section 4.0 of 1-SI-OPS-082-007.B is complete.
INITIATING CUES:
The U1 US/SRO has reviewed the completed work package for the 1B-B
remains is to perform 1-SI-OPS-082*007.B for the PMT.
You are an extra unit operator and have been assigned t o perform the operability run of
DIG 1B-B per SI-OPS-082-007.B.
The PMT requires the AMBIENT MANUAL START method for testing.
Notify the US when the test is complete.
}}