ML20055D830
| ML20055D830 | |
| Person / Time | |
|---|---|
| Issue date: | 06/25/1990 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | Hall W NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| References | |
| NUDOCS 9007100064 | |
| Download: ML20055D830 (59) | |
Text
S" 8
Juae 25,1990 s
Mr. Warren _ J. Hall, Manager
~0perations, Management and Support Services Division Nuclear Managen,ent end Resources Council 1776 Eye Street, Suite 300 Washington, D.C. 20000-2490
Dear Mr. Hall:
. Enclosed is the first draft for new EWR STS section 3.10 Special Operations.
EThis draft incorporates the results of our meeting with NUMARC and the BWR-Owners Group on May 9, 1990. We understand that the BWR Owners Group will 1
use this draft to prepare revised Bases for this new STS section and will submit the Bases to the staff in hard copy and on magnetic n.edia in Word
~
- Perfect 5.1 by August 3, 1990.
Sincerely, l
ORIGINAL SIGNED BY JOSE A.0ALVO Jose A. Calvo, Chief Technical Specifications Branth Division of Operational Events Assessaient, NPR fnclosure:
As stated cc:
C. DeDeaux, CEOG Chairman DISTRIBUTION: w/o Enclosure J. Hinds, WOG Chairwoman TEMurley CHBerlinger C. _ Siryth, B&WOG Chairman FJMiraglia PWBaranowsky J. Jones, BWROG Chairman WTRussell FGillespic E. Lorito, VEPC0 CERossi JLieberman B. koods, SCE JGPartlow ELJordan K. Wilson, FPC CMCrutchfield WGKennedy J. Fowler, SERI SAVarga MGMalsch M. Bryan, TVA GhHolahan OTSD Menibers J. Jones, GPC ACThadani OTSB R/F BKGrimes COEA R/F JWRoe FJCongel PDR w/ Enclosure Conran Central; files w/E c cs s
g DOCUMENT NAME: LTR HALL 3.9 REFUEL GILLES
- See previous concurrence n
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i Mr. Warren J. Hall, Manager Operations, Management and Support Services Division Nuclear Managenent and Resources Council 1776 Eye Street, Suite 300 Washington, D.C. 20006-2496
Dear Mr. Hall:
Enclosed is the first draft for new BWR STS section 3.10 Special Operations.
This draft incorporates the results of our meeting with NUMARC and the BWR.
Owners Group on April 13. 19S0. We understand that the BWR Owners Group will use this draft to prepare revised Bases for this new STS section and will s
submit the Bases to the staff in hard copy and on magnetic media in Word Perfect 5.1 by August 3, 1990.
l.
Sincerely, 1
Jose A. Calvo, Chief Technical Specifications Branch Division of Operational Events Assessment, NRR i
l
Enclosure:
As stated cc:
-C. DeDeaux, CEOG Chairman DISTRIBUTION: w/o Enclosure J. Hinds, WOG Chairwoman TEMurley CHBerlinger i
C. Smyth, B&WOG Chairs:an FJMiraglia PWBaranows ky J. Jones, BWROG Chairman WTRussell FGillespie E. Lozito. VEPC0 CERossi JLieberman i
B. Woods, SCE JGPartivw ELJordan K. Wilson, FPC DHCrutchfield WGKennedy J. Fowler, SERI SAVarga MGMalsch M. Bryan, TVA CMHolahan OTSB Members J. Jones, GPC ACThadani OTSB R/F BKGrimes DOEA R/F JWRoe FJCongel PDR w/ Enclosure Conran Central Files w/ Enclosure
-DOCUMENT NAME:
LTR HALL 3.9 REFUEL GILLES nv#
OTSB:00EA:NRR OTSB:00EA:NRR OTSB:00EA IRR C:0TSB:00EA:NRR NVGilles FMReinahrtfM' RMLobel JACalvo 7
06/Ja/90 06/32/90 06/22 / 0 06/ /90
L, i
4 Inservice Leak and Hydro Test 3.10.1 1
3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation-LC0 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 operation may be changed to "Any temperature" to allow performance of an inservice leak or hydrostatic test provided the following MODE 3 LCOs are met:
a.
LCO 3.3.6.2, Secondary Containment Isolation i
Instrumentation, Functions 1, 3, and 4 of Table 3.3.6.2-1.
b.
LCO 3.6.4.1, Secondary Containment.
c.
LC0 3.6.4.2, Secondary. Containment Isolation Valves.
i d.
LC0 3.6.4.3, Standby Gas Treatment System.
I 1
APPLICABILITY:
MODES 4 with average reactor coolant temperature > [200] F.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more of the A.1
NOTE--------
above required LCOs Required Actions to i
not met, be in MODE 4 include reducing average 4
reactor coolant temperature to I i
(200) F.
-y 1
Enter the applicable Immediately Condition of the affected LCOs.
OB 4
l (continued)
L-l BWR/4-3.10 1 06/15/90
o u..
Inservice Leak and Hydro Test 3.10.1
. ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.2.1 Suspend activities Immediately that could increase the average reactor coolant temperature or pressure.
AND I
i' A.2.2 Reduce average 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-reactor coolant temperature to
$ [200] 'F.
SURVEILLANCE REQUIREMENTS
[
SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the.equired According to N0DE 3 LCOs.
the applicable
(
1:
SRs L
l CROSS-REFERENCES TITLE NUMBER Secondary Containment Isolation Actuation Instrumentation 3.3.6.2 L
Secondary Containment 3.6.4.1 1
Secondary Containment Isolation Valves 3.6.4.2 Standby Gas Treatment System 3.6.4.3 BWR/4 3.10-2 06/15/90
i;;
Reactor Mode Switch Interlock Testing 3.10.2 3.10' SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testina LC0 3.10.2 The Reactor Mode Switch position specified in Table 1.1-1 for MODES 3, 4 and 5 operation may be changed to include the Run, Startup/ Hot Standby, and Refuel position to allow testing of instrumentation associated with the Reactor Mode Switch interlock functions provided all control rods remain fully inserted in core cells that contain one or more fuel i
assemblies and no other CORE ALTERATIONS are in progress.
j APPLICABILITY:
MODES 3 and 4 with the Reactor Mode Switch in the Run, Startup/ Hot Standby, or Refuel position, MODE 5 with the Reactor Mode Switch in the Run or Startup/ Hot Standby position.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1 Suspend CORE Immediately LC0 not met.
ALTERNATIONS except for control rod insertion.
AND A.2 Fully insert all I hour insertable control rods in core cells that contain one or more fuel i
assemblies.
I E
A.3.1 Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the L
Shutdown position.
l' E
(continued)
L BWR/4 3.10-3 06/15/90
Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS
]
CONDITION REQVIRED ACTION COMPLETION TIME A.
(continued)
A.3.2
NOTE-------
Not applicable in MODES 3 and 4.
Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the Refuel position.
SVRVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in core cells that contain one or more fuel assemblies.
SR 3.10.2.2 Verify no other CORE ALTERATIONS are in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> progress.
CROSS-
REFERENCES:
- None l
l BWR/4 3.10-4 06/15/90
i Single' Control. Rod Withdrawal - Hot Shutdown.
4 l
3.10.3 I'
13.10 SPECIAL OPERATIONS
- 3.10;3
.Sinole Control Rod Withdrawal - Hot Shutdown LC0 ~ 3.10.3 The Reactor Mode Switch position specified in Table 1.1-1 for MODE 3 operation may be changed to include the Refuel position to allow withdrawal of a single control rod provided the following requirements are met:
a..
LCO 3.9.2, Refuel Position One-Rod-Out Interlock.
b.
LC0 3.9.4, Control Rod Position Indication, c.
All other control rods are 't11y inserted.
d.
1.
LC0 3.3.1.1, MODE 5, Resctor Protection System Instrumentation, functions [1.a. 1.b, 2.a. 2.e, 11 and 12 of Table 3.3.1.1-1.]
(LC0 3.3.8.2, MODE 5, Reactor Protection System Electric Power Monitoring.]
LCO 3.9.5, Control Rod OPERABILITY - Refueling.
QB 2.
All other control rods in a five-by-five array centered on the control rod being withdrawn.are disarmed.
LC0 3.1.1, MODE 5, SHUTDOWN MARGIN, except the single control rod to be withdrawn may be assumed to be the highest worth control rod.
APPLICABILITY:
MODE 3 with the Reactor Mode Switch in the Refuel position.
BWR/4 3.10-5 06/15/90
n"~.
i yy
/
Single. Control Rod Withdrawal - Hot Shutdown 3.10.3
-l gv.
ACTIONS b'
CONDITION =
REQUIRED. ACTION COMPLETION TIME s.
A.
One or more of the A.1
.--------NOTE-above requirement; Required Actions to Pi not met.
fully insert all insertable control rods include placing
+l the Reactor Mode Switch in the Shutdown position.
Enter the applicable immediately.
Condition of the affected LCOs.
' D.B A.2.1 Fully insert all I hour insertable control rods.
AND A.2.2 Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the Shutdown position.
1.
~
l; I
o l
BWR/4 3.10-6 06/15/90 m
J.'>
Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY SR 3'10.3.1 Perform the applicable SRs for the required According to LCOs.=
the applicable SRs SR 3.10.3.2 Verify all other control rods in a five-by-24 hours five array centered on the control rod being withdrawn are disarmed.
L SR 3.10.3.3 Verify all other control rods are. fully 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
L CROSS-REFERENCES TITLE NUMBER SHUTDOWN MARGIN-3.1.1 t.
l Reactor Protection System Instrumentation 3.3.1.1 l
Reactor Protection System Electric Power Monitoring 3.3.8.2 b
Refuel Position One-Rod-Out Interlock 3.9.2 l
l-Control Rod Position Indication 3.9.4 L
1 Control Rod OPERABILITY - Refueling 3.9.5 l
BWR/4 3.10-7 06/15/90
a Single Control Rod Withdrawal - Cold-Shutdown 3.10.4 3.10-SPECIAL OPERATIONS 3.10. 4 ~-
Sinale Control Rod Withdrawal - Cold Shutdown LC0 3.10.4 The Reactor Mode Switch position specified in Table 1.1-1 for MODE 4 operation may be changed to include the Refuel position to allow withdrawal of. a single control rod or withdrawal and subsequent removal of ~ the. associated control rod drive provided the following requirements are met:
a.
All other control rods are fully inserted.
b.
1.
LCO 3.9.2, Refuel Position One-Rod-Out Interlock.
LC0 3.9.4, Control Rod Position Indication.
M 1.
2.
A control rod withdrawal block is inserted, c.
1.
LCO 3.3.1.1, MODE 5, Reactor Protection System Instrumentation, [ Functions 1.a. 1.b. 2.a, 2.e, 11 and 12 of Table 3.3.1.1-1].
[LCO 3.3.8.2, MODE 5, Reactor Protection System Electric Power Monitoring).
LC0 3.9.5, Control Rod OPERABILITY - Refueling.
M 2.
All other control rods in a five-by-five array centered on the control rod being withdrawn are disarmed.
c LC0 3.1.1, MODE 5, SHUTDOWN MARGIN, except the l
single control rod to be withdrawn may be assumed to be the highest worth control rod, APPLICABILITY:
MODES 4 with Reactor Mode Switch in the Refuel position, i
BWR/4 3.10-8 06/15/90 1:
L
n
~.,..
1
~
14.
b
?
P..
Single Control Rod Withdrawal - Cold Shutdown 3.10.4:
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 1
A.
One or more of the A.1
NOTE--------
above requirements Required Actions to not met with the fully insert all affected control rod insertable control
. insertable,
rods include placing the Reactor Mode Switch in the Shutdown position.
Enter the applicable immediately Condition of the affected LCOs.
QB i
A.2.1 Fully insert all I hour insertable control
- rods, bN.D A.2.2 Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the l'
Shutdown position.
i B.
One or more of the 0.1 Suspend withdrawal Immediately above requirements of the control rod not met with the and removal of affected control rod associated control not insertable, rod drive.
AND B.2.1 Initiate action to Immediately fully insert all control rods.
QB B.2.2 Satisfy the Immediately requirements of this LCO.
i BWR/4 3.10-9 06/15/90
Single Control Rod Withdrawal o Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS SURVEIL;ANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs.
the applicable SRs SR 3.10.4.2 Verify all other control rods in a five by-24 hours five array centered on the control rod being l
withdrawn are disarmed, i
SR 3.10.4.3 Verify all other control rods are fully 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
SR 3.10.4.4 Verify a control rod withdrawal block is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
CROSS-REFERENCES i
TITLE NUMBER l
SHUTDOWN MARGIN 3.1.1 Reactor Protection System Instrumentation 3.3.1.1 Reactor Protection System Electric Power Monitoring 3.3.8.2 Refuel Position One-Rod-Out Interlock 3.9.2 Control Rod Position Indication 3.9.4 Control Rod OPERABILITY - Refueling 3.9.5 BWR/4 3.10-10 06/15/90
o 4
Single Control Rod Drive Removal - Refueling 3.10.5 3.10~ SPECIAL OPERATIONS 3;10.5 Sinole Control Rod Drive Removal - Refuelina
-LC0- 3.10.5-The requirements of LCO 3.3.1.1 RPS Instrumentation, LCO 3.3.1.3 RPS Short Links, [LCO 3.3.8.2 RPS Electrical Power Monitoring], LCO 3.9.'l Refueling Equipment Interlocks, LC0
-3.9.2 Refueling Position One-Rod Out Interlock, LC0 3.9.4 Control Rod Positica Indication and LC0 3.9.5 Control Rod OPERABILITY - Refueling.may be suspended during MODE 5 operation to allow the removal of a single control rod drive associated with a control rod withdrawn from a core cell containing one or more fuel assemblies provided the following requirements are met:
a.
All other control rods are fully inserted.
b.
All other control rods in a five-by-five. array centered j
on the control rod being removed are disarmed.
c.
A control rod withdrawal block is inserted, d.
LC0 3.1.1, MODE 5, SHUTDOWN MARGIN, except the single control rod to be withdrawn may be assumed to be the highest worth' control rod.
e.:
No other CORE ALTERATIONS are in progress.
APPLICABILITY:
MODE 5 with LCO 3.3.5 Control Rod OPERABILITY - Refueling, not met.
l b
i BWR/4 3.10-11 06/15/90 l
i-j [6 :y.
[i.
Single Control Rod Drive Removal' - Refueling 3.10.5 e
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME m
A.
One or more of the A.1 Suspend removal of Immediately above requirements
.the control rod and not met, associated control rod drive mechanism.
AN,D A.2.1 Initiate action to Immediately fully insert all control rods.
- H 95 A.2.2 Satisfy the Immediately requirements of this LCO.
r BWR/4 10-12 06/15/90
Single Control Rod Drive Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS
' SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all other controls rods are fully 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
SR 3.10.5.2 Verify all control rods in a five-by-five 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> array centered on the control rod being removed are disarmed.
9 l
SR 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
'SR 3.10.5.4 Perform the applicable SRs for LC0 3.1.1.
According to the applicable SRs SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> progress.
I L
b l
l BWR/4 3.10-13 06/15/90 i=
a Single Control Rod Drive Removal - Refueling 3.10.5 CROSS-REFERENCES TITLE NUMBER SHUTDOWN MARGIN 3.1.1 Reactor Protection System Instrumentation 3.3.1.1 Reactor Protection System Shorting Links 3.3.1.3-Reactor Protection System Electric Power Monitoring 3.3.8.f Refueling Equipment Interlocks 3.9.1 l
Refuel Position One-Rod-Out Interlock 3.9.2 Control Rod Position Indication 3.9.4 Control Rod OPERABILITY - Refueling 3.9.5 BWR/4 3.10-14 06/15/90
y Multiple Control Rod Withdrawal -~ Refueling
.3.10.6 3.10' SPECIAL'0PERATIONS 3.10.6 Multiple Control Rod Withdrawal - Refuelina
'LC0 3.10.6 Two ' Full In" position. indicators may be bypassed for any number of control rods during MODE 5 operation to allow withdrawal of those control rods, removal of associated control rod drives or both provided the following requirements are met:
a.
The four fuel assemblies are removed from the core cells associated with each control rod or. control rod drive to be removed, b.
All other control rods in~ core cells containing one or more. fuel assemblies are fully inserted.
c.
Fuel assemblies shall only be loaded in compliance with an approved (spiral] reload sequence.
APPLICABILITY:
MODE 5 with LC0 3.9.3 Control Rod Position, LC0 3.9.4 Control Rod Position indication, or LC0 3.9.5 Control Rod OPERABILITY-Refueling, not met.
l BWR/4 3.10-15 6/15/90 1
l l
I Multiple Control-Rod Withdrawal - Refueling 4
3.10.6 1
' ACTIONS 9
' CONDITION REQUIRED ACTION
. COMPLETION TIME A.
Requirements of the' A.]
Suspend withdrawal Immediately LCO not met, of control rods and removal of associated control rod drives.
MD A.2.1 Initiate action to immediately fully insert all control rods in core cells containing one L
or more fuels assemb' lies.
DB A.2.2 Satisfy the immediately requirements of this LCO.
(continued) l l
l l
BWR/4 3.10-16 6/15/90 t
Multiple Control Rod Withdrawal - Refueling 3.10.6
~ SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
.,I I
SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from core cells associated with a control rod or control rod drive to be removed, j
i SR 3.10.6.2-Verify all other control rods in core cells 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> f
containing one or more fuel assemblies are
-l fully inserted.
---NOTE-------
l Only' required during fuel reloading.
I Verify fuel assemblies being loaded are in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> compliance with an approved [ spiral) reload i
sequence.
l I
f CROSS-REFERENCES TITLE NUMBER Control Rod Position Indication 3.9.4 BWR/4 3.10 17 6/15/90
f, Control Rod Testing Operating-3.10.7 h!
3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testino - Operatina e
LCO 3.10.7 The requirements of LCO 3.1.6 Rod Pattern Control may be suspended during MODES 1 and 2 with-THERMAL POWER less than or equal to the Low Power Set Point (LPSP) of the RWM to allow performance of SHUTDOWN MARGIN demonstrations, control' rod scram time testing, control rod friction testing, and the Startup Test Program provided:
a.
The approved control rod sequence for the specified test is programmed into the RWM and conformance is verified per SR 3.3.2.1.8, Control Rod Sequence Verification.
QB b.
The RWM is bypassed as allowed by LC0 3.3.2.1 Control Rod Block Instrumentation, and.conformance to the 4
approved control rod sequence for the specified test is verified by a second licensed operator or other l
i qualified member of the technical staff, i
APPLICABILITY:
MODES 1 and 2 with LCO 3.1.6 Rod Pattern Control,-not met.
(
ACTIONS l
CONDITION REQUIRED ACTION COMPLETION-TIME 9
A.
Requirements of the A.1 Suspend performance immediately l
LC0 not met, of the test and t
exception to LC0 3.1.6, Rod Pattern Control.
l BWR/4 3.10-18 6/15/90
.' T 61; Control Rod Testing - Operating-3.10.7 SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY j
..................N0TE---------------
SR 3.10.7.1 Not required if SR 3.10.7.2 satisfied.
t h
r Verify movement of control rods is in During control compliance with the approved control rod rod movement 1
sequence for the specified test.
.................-N0TE-----------------
SR 3.10.7.2 Not required if SR 3.10.7.1 satisfied.
k Verify control rod sequence input to the RWM Prior to is in conformance-with the approved control control rod rod sequence for the specified test.
movement CROSS-REFERENCES' i
TITLE NUMBER
~ Rod Pattern Control 3.1.6 Control Rod Block Instrumentation 3.3.2.1 1
l l
BWR/4 3.10-19 6/15/90
.~..
C
+
e
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Primary Containment'- PHYSICS TESTS 1
3.10.8 3.10' SPECIAL OPERATIONS 3.10.8=
Primary Containment - PHYSICS TESTS LC0 3.10.8 The reactor head bolt status specified in Table 1.1-1 for MODE 2. operation may be changed to allow the vessel head to be removed, and LCOs 3.6.1.1 Primary Containment, 3.6.1.2 Primary Containment Air Lock, 3.4.3 Safety / Relief Valves, 3.3.6.5 Low-Low Set Instrumentation, 3.6.18 Low-Low Set.
Safety Relief Valves, and Functions 9 and 10 of LC0 3.3.3.1 Post-Accident Monitoring Instrumentation, may be suspended to allow PHYSICS TESTS provided the following requirements are met:.
a.
All OPERABLE IRM channels are 1 [ 25/40 ) divisions of full scale on Range 7.
1, b.
Reactor coolant temperature is < 200'F.
APPLICABILITY:
MODE 2 with the reactor head bolts not fully tensioned.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i-A.
One or more of the A.1 Place the Reactor immediately l
above requirements Mode Switch in the not met.
Shutdown position.
L BWR/4 3.10-20 6/15/90 L
a Primary Containment - PHYSICS TESTS 1
3.10.8 i
r...
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Verify all OPERABLE IRM channels are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> s [ 25/40 ) divisions of full scale on Range 7.
l t
SR 3.10.8.2 Verify reactor coolant temperature is I hour s
< 200'F.
CROSS-REFERENCES TITLE
-NUMBER Post-Accident Monitoring Instrumer.tation 3.3.3.1 Low-Low Set Instrumentation.
3.3.6.5 Safety /ReliefValves
'3.4.3 Primary Containment 3.6.1.1 Primary Containment Air Lock-3.6.1.2 Low-Low Set Safety / Relief Valves 3.6.1.8 1
BWR/4 3.10-21 6/15/90
9 4
kv. -
74 Shutdown Margin Test - MODE 5 4
9 3.10.94 3.10 SPECIAL-OPERATIONS 3.10.9 Shutdown Marain Test - MODE 5 LCO 3.10.9 The Reactor Mode Switch position specified in Table 1.1-1 for MODE 5 operation may be changed to include the Startup/ Hot Standby position to allow Shutdown Margin I
testing provided the following requirements,are met:
i a.
1.
LC0 3.3.2.1 Control Rod Block Instrumentation, h
Function 2 for MODE 2, with the [ BPWS ]
i.
requirements of SR 3.3.2.1.8 changed to require the-control rod sequence to conform to the shutdown margin test sequence, n;
QB 2.
Conformance to the shutdown margin. test sequence is verified by a second licensed operator or other qualified member of the technical staff.
}
b.
All control rod withdrawals [during out-of-sequence control rod moves) shall be made in notch out mode, c.
No other CORE ALTERATIONS are in progress.
APPLICABILITY:
. MODE 5 with the Reactor Mode Switch in Startup/ Hot Standby position.
ASIONS CONDITION REQUIRED ACTION-COMPLETION TIME 1
f A.
One or'more of the A.1 Place the Reactor-Immediately above requirements Mode Switch in the not met.
Shutdown or Refuel
- position, i
l I'
l BWR/4 3.10-22 6/15/90 J
\\
Shutdown Margin Test - MODE 5 3.10.9
. SURVEILLANCE RE'QUIREMENTS SURVEILLANCE FREQUENCY
..................N0TE----------
SR 3.10.9.1 Not required if SR 3.10.9.2 satisfied.
T-Perform the applicable SRs for the required According to LCOs.
the applicable SRs
..................N0TE-----
SR 3.10.9.2 Not required if SR 3.10.9.1 satisfied.
Verify movement of control rods 'is in During control' compliance with the approved control rod rod movement sequence-for the shutdown margin test.
SR 3.10.9.3 Verify no other-CORE ALTERATIONS are in
!? hours progress.
CROSS-REFERENCES TITLE NUMBER Control Rod Block Instrumentation 3.3.2.1 BWR/4 3.10-23 6/15/90
i 1
4-Recirculation Loops - Testing 3.10.10 3.10 SPECIAL OPERATIONS 3.10.10 Recirculation loops - Testina p.
LCO 3.10.10 The requirements of LCO 3.4.1, Recirculation Loops -
Operating, may be suspended for 124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> to allow:
a.
. PHYSICS TESTS provided THERMAL POWER is s [ 5 ]% of RTP.
b.
Performance of the Startup Test Program.
APPLICABILITY:
MODES 1 and 2 with less than two recirculation loops in
. operation.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME-A.
Requirements of LC0 A.1 Insert all
[ l ] hour
-3.4.1 not met for insertable control
> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
rods.
B.
Requirements of the B.1 Place the Reactor
'Immediately LC0 not met for Mode Switch in the reasons other than Shutdown position.
Condition A.
t L
BWR/4 3.10-24 6/15/90
^
Recirculation Loops Testing -
3.10.10 SURVEILLA!!CERE00lREMENTS _ _ _ _ _. __
SURVEILLANCE FREQUENCY SR 3.10.10.1 Verify LC0 3.4.1 Recirculation loops -
I hour Operating, requirements suspended for 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SR 3.10.10.2 Verify THERMAL POWER is 1 [ 5 ]Y. of RTP 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during PHYSICS TESTS.
CROSS-REFERENCES TITLE NUMBER Recirculat' ion Loops Operating 3.4.1 l-BWR/4 3.10-25 6/15/90 1
2-1 Training Startups 3,10.11 E3.10 SPECIAL OPERATIONS
'3.10.11 Trainina Startuos LC0 3.10.11 The' LPCI OPERABILITY requirements specified in LC0 3.5.l' may be changed to allow one RHR subsystem to be aligned.in the shutdown cooling mode for training startups provided the i
following requirements are met:
a.
All OPERABLE 1RM channels are s [ 25/40 ] divisions of full scale on Range 7.
b.
Reactor coolant temperature is <'200'F.
i t
APPLICABILITY::
MODE 2 with one LPCI subsystem suction valve closed.
l ACTIONS 1
CONDITION REQUIRED ACTION COMPLETION TIME j
A.
One or more of the A.1 Place the Reactor immediately above requirements Mode Switch in the not met.
Shutdown position, i
SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY j
)
SR 3.10.11.1 Verify all OPERABLE IRM channels are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
1 [ 25/40 ) divisions of full scale on Range 7.
SR 3.10.11.2 Verify reactor coolant temperature is I hour i
l
<-200*F.
l t
l l
L 1
BWR/4 3.10-26 6/15/90 l
7 n.
t..-
l Training Startups 3.10.11 t
CROSS REFERENCES TITLE NUMBER ECCS - Operatin9 3,5.1 l
-l
-l i
l l
BWR/4 3.10 27 6/15/90 i
- m i
a r.
Oxygen Concentration Startup Test Program 3.10.12 3.10 SPECIAL OPERATIONS 3.10.12 0xvoen Concentration Star +un Test Proaram LCO 3.10.12 The requirements of LC0 3.6.3.3 Primary Containment Oxygen Concentration, may be suspended to allow performance of the Startup Test Program.
APPLICABILITY:
s 120 Effective Full Power Days (EFPD) of operation.
ACTIONS CONDITION-REQUIRED ACTION COMPLETION TIME A.
The above requirement A.1 Enter the applicable immediately not met.
Condition of the affected LCO.
I SVRVEILLANCE RE0VIREMENTS SURVEILLANCE FREQUENCY SR 3.10.12.1 Verify operation s 120 EFPD.
7 days.
CROSS-REFERENCES TITLE NUMBER Primary _ Containment Oxygen Concentration 3.6.3.3 l
l BWR/4 3.10 28 6/15/90 i
t I
c>
Inservice Leak and Hydro Test 3.10.1 i
4 3.10 SPECIAL OPERATIONS 3.10.1-Inservice leak and Hydrostatic Testina Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1 1 for MODE 4 operation may be changed to "Any temperature" to allow performance of an inservice leak or hydrostatic test provided the following MODE 3 LCOs are met:
a.
LCO 3.3.6.2, Secondary Containment Isolation Instrumentation, functions 1, 3, and 4 of Table i
3.3.6.2 1.
1 l
b.
LCO 3.6.4.1, Secondary Containment.
c.
LC0 3.6.4.2, Secondary Containment Isolation Valves, d.
LCO 3.6.4.3, Standby Gas Treatment System.
APPLICABILITY:
MODES 4 with average reactor coolant temperature > [200)'F.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more of the A.)
NOTE------ -
1 above required LCOs Required Actions to
.not met.
be in MODE 4-include reducing average reactor coolant temperature to 1
[200]'F.
Immediately Enter the applicable Condition of the i
L affected LCOs.
D.8 j-(continued)
BWR/6 3.10 1 06/15/90
s o
t
' Inservice Leak and Hydro Tes* -
l 3.10.1 s.
ACTIONS (continued) j CONDITION REQUIRED ACTION COMPLETION TIME A.
(continued)
A.2.1 Suspend activities Immediately that could increase the average reactor coolant temperature or pressure.
6!!Q A.2.2 Reduce average 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reactor coolant temperature to 1 [200) 'F.
q i
j SURVEILLANCE RE0VIREMENTS SVRVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to
. MODE 3 LCOs.
the applicable SRs j
r 1
r l-1 4
i h
BWR/6 3.10-2 06/15/90
I*
Inservice Leak and Hydro Test 3.10.1 CROSS REFERENCES TITLE NUMBER Secondary Containment Isolation Actuation Instrumentation 3.3.6.2 Secondary Containment 3.6.4.1 Secondary Containment isolation Valves 3.6.4.2 Standby Gas Treatment System 3.6.4.3 l
1.
l l.
l-i BWR/6 3.10 3 06/15/90
L
,e l
i Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS l
3.10.2-Er. actor Mode Switch Interlock Testina I
LCO 3.10.2 The Reactor Mode Switch position specified in Table 1.1-1 for MODES 3, 4 and 5 o)eration may be changed to include the Run, Startup/ Hot Standay, and Refuel position to allow testing of instrumentation associated with the Reactor Mode Switch interlock functions provided all control rods remain fully inserted in core cells that contain one or more fuel y
assemblies arid no other CORE ALTERATIONS are in progress.
i APPLICABILITY:
MODES 3 and 4 with the Reactor Mode Switch in the Run, Startup/ Hot Standby, or Refuel position, MODE 5 with the Reactor Mode Switch in the Run or Startup/ Hot Standby position.
ACTIONS CONDITION RE0VIRED ACTION COMPLETION TIME A.
Requirements of the A.1 Suspend-CORE 1mmediately LCO not met.
ALTERNATIONS except for control rod insertion.
BED A.2 fully insert all I hour insertable control rods in core cells that contain one or more fuel assemblies, BED y
A.3.1 Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the Shutdown position.
93 o
(continued)
L BWR/6 3.10-4 06/15/90
-5
_y,.
j,4 Reactor Mode Switch Interlock Testing 3.10.2 I
j ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
)
-A.
-(continued)
A.3.2
NOTE-------
Not applicable in MODES 3 and 4.
Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the 1
Refuel position.
J i
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in core cells that contain one or more fuel assemblies.
.SR 3.10.2.2 Verify no other CORE ALTERATIONS are in
' 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> progress.
i CROSS
REFERENCES:
None j
o r
l' BWR/6 3.10-5 06/15/90
i j
I_
+
Single Control Rod Withdracal - Hot Shutdown L
3.10.3 2.
3.10 SPECIAL OPERATIONS 3
f 3.10.3 Single Control Rod Withdrawal - Hot Shutdown LCO 3.10.3 The Reactor Mode Switch position specified in Table 1.1 1 for MODE 3 operation may be changed to include the Refuel position to allow withdrawal of a single control rod provided the following requirements are met:
i a.
LCO 3.9.2, Refuel Position One Rod Out Interlock, b.
LCO 3.9.4, Control Rod Position Indication.
c.
All other control rods are fully inserted.
l d.
1.
LCO 3.3.1.1, MODE 5, Reactor Protection System
}
L Instrumentation, functions (l.a 1.b, 2.a. 2.e, 11 and 12 of Table 3.3.1.1-1.]
[LCO 3.3.8.2, MODE 5, Reactor Protection = System Electric Power Monitoring.]
LC0 3.9.5, Control Rod OPERABILITY Refueling.
i 08 l
2.
All other control rods in a five by-five array l
centereoaon the control rod being withdrawn are disarmed.
LC0 3.1.1, MODE 5, SHUTDOWN MARGIN, except the single control rod to be withdrawn may be assumed to be.the highest worth control rod.
APPLICABILITY:
MODE 3 with the Reactor Mode Switch in the Refuel position.-
t t
i L BWR/6 3.10 6 06/15/90 y
1.
.e l
i "f
Single Control Rod Withdrawal - Hot Shutdown 3.10.3 l
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME j
A.
One or more of the A.1
.. NOT E - - - - - -
above requirements Required Actions to t
not met, fully insert all insertable control rods include placing i
the Reactor Mode Switch in.the Shutdown position.
Enter the applicable Immediately Condition of the affected LCOs.
QB A.2.1 Fully insert all I hour i
insertable control rods.
S
+
t A.2.2 Place the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Mode Switch in the Shutdown position.
l t
BWR/6 3.10-7 06/15/90 m~,
r--,..,
e
V'
+
Single Control Rod Withdracal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required According to LCOs.
the applicable SRs SR 3.10.3.2 Verify all other control rods in a five by-24 hours' l
five array centered on the control rod being withdrawn are disarmed.
SR 3.10.3.3 Verify all other control ods are fully 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
i CROSS REFERENCES TITLE NUMBER s
SHUTDOWN MARGIN 3.1.1 Reactor Protection System Instrumentation 3.3.1.1 Reactor Protection System Electric Power Monitoring 3.3.8.2 Refuel Position One Rod-Out Interlock 3.9.2 Control Rod Position Indication 3.9.4
_ Control _ Rod OPERABILITY - Refueling 3.9.5 BWR/6 3.10-8 06/15/90
Iq Single Control Rod Withdrawal - Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Sinale Control Rod Withdrawal Cold Shutdown LCO 3.10.4 The Reactor Mode Switch position specified ta Table 1.1-1 for MODE 4 operation may be changed to include the Refuel position to allow withdrawal of a single control rod or i
withdrawal and subsequent removal of the associated control rod drive provided the following requirements are met:
a.
All other control rods are fully inserted, i
b.
1.
LCO 3.9.2, Refuel Position One Rod-Out Interlock.
LCO 3.9.4, Control Rod Position Indication.
M 2.
A control rod withdrawal block is inserted.
[
t c.
1.
LCO 3.3.1.1, MODE 5, Reactor Protection System Instrumentation, [ Functions 1.a. 1.b, 2.a. 2.e, 11 and 12 of Table 3.3.1.1-1).
l e
(LCO 3.3.8.2, MODE 5, Reactor Protection System l
Electric Power Monitoring).
LC0 3.9.5, Control Rod OPERABILITY - Refueling.
E l
2.
All other control rods in a five by-five array l
centered on the control rod being withdrawn are disarmed.
i LC0 3.1.1, MODE 5, SHUTDOWN MARGIN, except the-single control rod to be withdrawn may be assumed to i
be the highest worth control rod.
I l
APPLICABILITY:
MODES 4 with Reactor Mode Switch in the Refuel position.
BWR/6 3.10-9 06/15/90
t.
l.
Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more of the A.1
.----... NOTE- ------
above requirements Required Actier.3 to not met with the fully ins;rt all affected control rod insertable control insertable, rods include placing the Reactor Mode Switch in the Shutdown position.
Enter the applicable immediately l
Condition of the affected LCOs.
fB A.2.1 Fully insert all I hour insertable control rods.
MQ A.2.2 Place the Reactor I hour Mode Switch in the Shutdown position.
a I
B.
One or more of the B.)
Suspend withdrawal Immediately above requirements of the control rod not met with the and removal of affected control rod associated control not insertable, rod drive.
(
MQ B.2.1 initiate action to Immediately i
fully insert all control rods.
E l
B.2.2 Satisfy the immediately requirements of this LCO.
i BWR/6 3.10 10 06/15/90 l
Single Control Rod Withdracal Cold Shutdown 3.10.4 SVRVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required According to LCOs.
applicable SRs SR 3.10.4.2 Verify all other control rods in a five by-24 hours five array centered on the control rod being withdrawn are disarmed.
SR 3.10.4.3 Verify all other control rods are fully 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- inserted, i
SR 3.10.4.4 Verify a control rod withdrawal block is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
i CROSS REFERENCES TITLE NUMBER SHVTDOWN MARGIN 3.1.1 l
Reactor Protection System Instrumentation 3.3.1.1 Reactor Protection System Electric Power Monitoring 3.3.8.2 Refuel' Position One Rod Out Interlock 3.9.2 Control Rod Position Indication 3.9.4 Control Rod OPERABillTY Refueling 3.9.5
=
l-BWR/6 3.10 11 06/1S/90
4,.
c Single Control Rod Drive Removal - Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10,5-Sinole Control Rod Drive Removal - Refuelina LCO 3.10.5 The requirements of LCO 3.3.1.1 RPS Instrumentation, LCO 3.3.1.3 RPS Short Links, [LCO 3.3.8.2 RPS Electrical Power Monitoring), LCO 3.9.1 Refueling Equipment Interlocks, LCO 3.9.2 Refueling Position One+ Rod Out Interlock, LCO 3.9.4 Control Rod Position Indication and LCO 3.9.5 Control Rod OPERABILITY - Refueling, may be suspended during MODE 5 operation to allow the removal of a single control rod drive associated with a control rod withdrawn from a core cell containing one or more fuel assemblies provided the following requirements are met:
a.
All other control rods are fully inserted.
~b.
All other control rods in a five-by-five array centered on the control rod being removed are disarmed.
c.
A control rod withdrawal block is inserted, d.
LCO 3.1.1, MODE 5, SHUTDOWN MARGIN, except the single control rod to be withdrawn may be assumed to be the highest worth control rod.
-l l
e.
No other CORE ALTERATIONS are in progress.
APPLICABILITY:
MODE $ with LCO 3.9.5 Control Rod OPERABILITY - Refueling, l
not met.
i i
i BWR/6 3.10-12 06/15/90
o Single Control Rod Drive P.emoval + Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more of the A.1 Suspend removal of Immediately above requirements the control rod and not met.
associsted control rod drive mechanism.
8!!Q A.2.1 Initiate action to immediately fully insert all control rods.
DE A.2.2 Satisfy the immediately requirements of this LCO BWR/6 3.10-13 06/15/90
(
y,;E' :. I,
w.:
. Or Single Control Rod Drive Removal - Refueling e
b 3.10.5
$URVElLLANCE REQUIREMENTS aw
$URVEILLANCE FREQUENCY SR 3.10.5.1 Verify all other controls rods are fully 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
' inserted.
SR 3.10.5.2 Verify all control rods in a five by five 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> array centered on the control rod being removed'are disarmed.
SR' 3.10.5.3 Verify a control rod withdrawal block is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inserted.
SR 3.10.5.4 Perform the applicable SRs for LC0 3.1.1.
According to applicable SRs SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-progress.
L 1
l BWR/6 3.10-14 06/15/90 1
+
6
+
Sing:e Control Rod Drive Removal - Refueling
'. 10.5 l
CROSS-REFERENCES l
TITLE t[VMBER SHUTDOWN MARGIN 3.1.1
[
Reactor Protection System Instrumentation 3.3.1.1 Reactor Protection System Shorting _tinks 3.3.1.3
-Reactor Protection System Electric Power Monitoring 3.3.8.2
-l Refueling Equipment Interlocks 3.9.1 Refuel Position'One Rod Out Interlock 3.9.2 Control Rod Position-Indication 3.9.4 Control Rod OPERABILITY - Refueling 3.9.5_
(
t t
2
..I e
E BWR/6 3.10 15 06/15/90
Multiple Control Fod Withdrawal - Refueling 3.10.6 4
3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal - Refuelina LCO 3.10.6 Two " Full In" position indicators may be bypassed for any number of control rods during MODE 5 operation to allow withdrawal of those control rods, removal of associated control rod drives or both provided the following requirements are met:
a.
The four fuel assemblies are removed from the core cells associated with each control rod or control rod drive to be removed, b.
All other control rods in core cells containing one or more fuel assemblies are fully inserted.
c.
Fuel assemblies shall only be loaded in compliance with an approved (spiral] reload sequence.
APPLICABILITY:
MODE 5 with LCO 3.9.3 Control Rod Position, LCO 3.9.4 Control Rod Position Indication, or LC0 3.9.5 Control Rod OPERABILITY Refueling, not met.
BWR/6 3.10-16 6/15/90
1 l
-)
- O l
i b
Multiple Control Rod Withdrawal - Refueling 3.10.6 l
-ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1 Suspend withdrawal Immediately j
LCO not met, of control rods and removal of 1
associated control
.l
[
rod drives.
i AND lL A.2.1 Initiate action to Immediately L
fully insert all o
control rods in core I
cells containing one or more fuels assemblies.
l E3 i
1 o
A.2.2 Satisfy the immediately requirements of this i
- LCO, i
o i
-I 7
i h
E i
=>
f 5
BWR/6 3.10 17 6/15/90
)
Multiple Control Rod Withdrawal - Refueling 3.10.6
<r SURVEILLANCE RE0VIREMENTS l
I SURVEILLANCE FREQUENCY l
SR 3.10.6.1 Verify the four fuel assemblies are removed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from core cells associated with a control I
rod or control rod drive to be removed.
]
i e
i SR 3.10.6.2 Verify all other control rods in core cells 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l
containing one or more fuel assemblies are fully inserted.
--- ---- NOTE ----
Only required during fuel reloading.
+
t Verify fuel assemblies being(loaded are in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> compliance v:ith an approved spiral) reload
- sequence, p
e f
CROSS REFERENCES TITLE N'JMBER Control Rod Position Indication 3.9.4 i
t I
BWR/6 3.10 18 6/15/90
Control Rod Testing o Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testina - Operatino LCO 3.10.7 The requirements of LCO 3.1.6 Rod pattern Control, may be suspended and control rods bypassed in RACS as allowed by SR 3.3.2.1.9 Control Rod Bypass and Movement Verification, during MODES I and 2 with THERMAL POWER less than or equal to the LPSP of the Rod Pattern Control System to allow
{'
performance of SHUTDOWN MARGIN demonstrations, control rod scram time testing, control rod friction testing, and the Startup Test Program provided conformance with the control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.
APPLICABILITY:
MODES I and 2 with LC0 3.1.6 Rod Pattern Control, not met.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the A.1 Suspend performance Immediately LC0 not met, of the test and exception to LCO 3.1.6, Rod Pattern Control.
SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQVENCY SR 3.10.7.1 Verify movement of control rods is in During control compliance with the approved control rod rod movement sequence for the specified test.
BWR/6 3.10 19 6/15/90 g
[-:
r-Control Rod Testing o Operating 3.10.7 CROSS-REFERENCES TITLE NUMBER Rod Pattern Control 3.1.6 Control Rod Block Instrumentation 3.3.2.1 s:
.BWR/6-3,10 20 6/15/90 G
a Primary Containment - PHYSICS TESTS 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 Primary Containment PHYSICS TESTS LCO 3.10.8 The reactor head bolt status specified in Table 1.1-1 for MODE 2 operation may be changed to allow the vessel head to be removed, and LCOs 3.6.1.1 Primary Containment, 3.6.1.2 Primary Containment Air Lock, 3.4.3 Safety / Relief Valves, 3.3.6.5 Low-Low Set Instrumentation, 3.6.18 Low Low Set Safety Relief Valves, and functions 9 and 10 of LCO 3.3.3.1 Post-Accident Monitoring Instrumentation, may be suspended to allow PHY51CS TESTS provided the following requirements are met:
a.
All OPERABLE IRM channels are s ( 25/40 ) divisions of full scale on Range 7.
j b.
Reactor coolant temperature is < 200'F.
I APPLICABILITY:
MODE 2 with the reactor head bolts not fully tensioned.
ACTIONS CONDITION REQUIRED ACl10N COMPLETION TIME l
A.
One or more of the A.1 Place the Reactor Immediately I
I above requirements Mode Switch in the not met.
Shutdown position.
i BWR/6 3.10-21 6/15/90 i
[
4 Primary Containment PHYSICS TESTS
- c 3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCf.
FREQUENCY v
SR 3.10.8.1 Verify all OPERABLE 1RM channels are I hour s ( 25/40 ) divisions of full scale on Range 7.
SR 3.10.8.2 Verify reactor coolant temperature is I hour
< 200*F.
CROSS REFERENCES TITLE NUMBER Post-Accident Monitoring Instrumentation 3.3.3.1 Low Low Set Instrumentation 3.3.6.5 Safety / Relief Valves 3.4.3 Pri a y Containment Air Lock 3.6.1.2 Low Low Set Safety / Relief Valves 3.6.1.8 l
1 BWR/6-3.10-22 6/15/90
o Shutdown Margin Test MODE 5 3.10.9 3.10 SPECIAL OPERAT10NS 3.10.9 Shutdown Maroin Test - MODI _5 LCO 3.10.9 The Reactor Mode Switch position specified in Table 1.1-1 for MODE 5 operation may be changed to include the Startup/ Hot Standby position to allow Shutdown Margin testing provided the following requirements are met:
a.
1.
LCO 3.3.2.1 Control Rod Block Instrumentation, Function 2 for MODE 2, with the [ BPWS )
requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the shutdown margin test sequence.
E8 2.
Conformance to the shutdown margin test sequence is verified by a second licensed operator or other qualified member of the technical staff, b.
All control rod withdrawals [during out-of-sequence control rod moves) shall be made in notch out mode, c.
No other CORE ALTERATIONS are in progress.
APPLICABILITY:
MODE 5 with the Reactor Mode Switch in Startup/ Hot Standby position.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more of the A.1 Place the Reactor immediately above requirements Mode Switch in the not met.
Shutdown or Refuel position.
BWR/6 3.10 23 6/15/90
o-o.
I Shutdown Margin Test - MODE 5 3.10.9 i
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1
SR 3.10.9.1 NOTE--- --------------- -
i Not required if SR 3.10.9.2 satisfied.
Perform the applicable SRs for the required According to LCOs.
the applicable SRs i
- --- NOTE------ -------------
Not required if SR 3.10.9.1 satisfied, i
l Verify movement of control rods is in During control
)
compliance with the approved control rod rod movement sequence for the shutdown margin test.
SR 3.10.9.3 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> progress.
CROSS REFERENCES TITLE NUMBER i
Control Rod Block Instrumentation-3.3.2.1
- 'l T
k I
BWR/6 3.10-24 6/IS/90
e...
4 Recirculation Loops - Testing 3.10.10 3.10 SPECIAL OPERATIONS 3.10.10 Recirculation looos - Testina LCO 3.10.10 The requirements of LCO 3.4.1, Recirculation loops -
Operating, may be suspended for 124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> to allow:
a.
PHYSICS TESTS provided THERMAL POWER is s-[ 5 ]% of RTP.
. b.
Performance of the Startup Test Program.
APPLICABILITY:
MODES 1 and 2 with less than two recirculation loops in operation.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME-A.
Requirements of LCO A.1 Insert all
[ l ) hour 3.4.1 not met for insertable control
> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, rods.
B.
Requirements of the B.1 Place the Reactor Immediately LC0 not met for Mode Switch in the reasons other than Shutdown position.
Condition A.
l i
1 I
BWR/6 3.10-2S 6/15/90
p
.t
- e Recirculation Loops - Testing 3.10.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 1
SR 3.10.10.1 Verify LCO 3.4.1 Recirculation Loops.
I hour Operating, requirements suspended for 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SR 3.10.10.2 Verify THERMAL POWER is s ( 5 )% of RTP 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during PHYSICS TESTS.
i i
l CROSS REFERENCES TITLE NUMBER Recirculatioi, Loops Operating 3.4.1 i
l
-l i
BWR/6 3.10 26 6/15/90 i
I I.
ic va :,
Training Startups-3.10.11 1
s.
3.10 SPECIAL OPERATIONS q
3.10.11:
Trainino Startuos-LC0_
-3.10.11 The LPCI OPERABILITY requirements specified in LCO 3.5.1 may be changed to allow one RHR subsystem to be aligned in the shutdown cooling mode for training startups provided the following requirements are met:
a.
All OPERABLE IRM channels are s [ 25/40 ) divisions of full scale on Range 7.
t M.
Reactor coolant temperature is < 200'F.
APPLICABILITY:
MODE 2 with one LPCI subsystem suction valve closed.
ACTIONS-CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more of the A.1 Place the Reactor immediately above requirements Mode Switch in the not met.
Shutdown position.
-SURVEILLANCE REQUIREMENTS SVRVEILLANCE FREQUENCY-m-
SRE 3.10.ll.1 Verify all OPERABLE IRM channels are I hour
$_ [ 25/40 ) divisions of full scale on Range 7.
SR 3.10.11.2 Verify reactor coolant temperature is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
< 200'F.
4 n
BWR/6 3.10-27 6/15/90
a ;. y r.
Training Startups 3.10.11
. CROSS-REFERENCES TITLE NUMBER a:
L.
ECCS - Operating 3.5.1 l
1 f
i :'
I I
s 4
i C
e BWR/6 3.10-28 6/15/90
.:i
b<*
o
.=
0xygen Concentration - Startup Test Program 3.10.12 3.10 SPECIAL OPERATIONS 3.10.12 0xvoen Concentration - Startuo Test Prooram LCO' 3.10.12 The requirements of LCO 3.6.3.3 Primary Containment Oxygen Concentration, may be suspended to allow performance of the Startup Test Program.
APPLICABILI?Y:
s iJO Effective Full Power Days (EFPD) of operation.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
The above requirement A.1 Enter the applicable Immediately not met.
Condition of the affected LCO.
l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.12.1 Verify operation s 120 EFPD.
7 days l
l' i
CROSS-REFERENCES TITLE NUMBER l-l Primary Containment Oxygen Concentration 3.6.3.3 l
l l;
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BWR/6 3.10-29 6/15/90 l
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