ML20247R708
| ML20247R708 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/25/1989 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20247R706 | List: |
| References | |
| NUDOCS 8906070293 | |
| Download: ML20247R708 (16) | |
Text
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1 3/4.1 REACTIVITY CONTROL SYSTEMS-3/4.1.1' SHUTDOWN MARGIN .j
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LIMITING CONDITION FOR OPERATION 3.1.1 The SHUTDOWN MARGIN shall be equal.to or greater than: I
- a. 0.38% delta k/k with the highest worth rod analytically determined, or
- b. 0.28% delta k/k with the highest worth rod determined by test.
APPLICABILITY: OPERATIONAL CONDITIONS
\ 1, 2 , 3k 4k and 5\ l ACTION:
With the SHUTDi?WN MARGIN less than specified:
- a. In OPERATIONAL CONDITION 1 or 2, reestablish the required SHUTDOWN MARGIN within 6 hours or be in at least HOT SHUTDOWN within the next 12 hours.
- b. In OPERATIONAL CONDITION 3 or 4, immediately verify all insertable control rods to be inserted and suspend all activities that could reduce the SHUTDOWN MARGIN. In OPERATIONAL CONDITION 4, establish SECONDARY CONTAINMENT INTEGRITY within 8 hours.
k c. In OPERATIONAL CONDITION 5, suspend CORE ALTERATIONS
- and other activities that could reduce the SHUTDOWN MARGIN, and insert all insertable control rods within 1 hour. Establish SECONDARY CONTAINMENT INTEGRITY within 8 hours.
SURVEILLANCE REQUIREMENTS 4.1.1 The SHUTDOWN MARGIN shall be determined to be equal to or greater than specified at any time during the fuel cycle: ,
- s. By measurement, prior to or during the first startup after each refueling.
- b. By measurement, within 500 MWD /T prior to the core average exposure at which the predicted SHUTDOWN MARGIN, including uncertainties and calculation biases, is equal to the specified limit.
- c. Within 12 hours after detection of a withdrawn control rod that is 1 immovable, as a result.of excessive friction or mechanical inter-ference, or is untrippable, except that the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable coatrol rod.
' "Except movement of IRMs, SRMs er speciel movable detectors.
#See Special Test Exception 3.1
. LA SALLE - UNIT 2 3/4 1-1 Amendment No. 30 8906070293 890525 PDR ADOCK 05000374 P PDC _ - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ - _
n-REACTIVITY CONTROL SYSTEM 3/4.1.3 CONTROL RODS
.[ CONTROL ROD OPERABILITY LIMITING CONDITION FOR OPERATION 3.1.3.1 All control rods shall be OPERABLE.
APPLICABILITY: OPERATIONALCONDITIONS1$and2D .l ACTION:
- a. With one control rod inoperable due to being immovable, as a result of-excessive friction or mechanical interference, or known to be untrippable:
- 1. Within 1 hour:
a) Verify that the inopsrable control rod, if withdrawn, is' separated fron, all other inoperable control rods by at-least two control cells in all directions. b) Disarm the associated directional control valves
- either: .
- 1) Electrically, or
'2) Hydraulically by closing the drive water and exhaust water isolation valves.
c) Comply with Surveillance Requirement 4.1.1.c.
- 2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours.
- 3. Restore the inoperable control rod to OPERABLE status within
_' 48 hours or be in at least HOT SHUTDOWN within the next 12 hours.
- b. With one or more control rods trippable but inoperable for causes other than addressed in ACTION a, above:
' 1. If the inoperable control rod (s) is withdrawn:
a) Immediately verify:
- 1) That the inoperable withdrawn control rod (s) is separated from all other inoperable withdrawn control rod (s) by at least two control cells in all directions, ,
and
- 2) The insertion capability of the inoperable withdrawn control rod (s) by inserting the control rod (s) at ir.ast-one notch by drive water pressure within the normal operating range **.
b) Otherwise, insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves
- either:
- 1) Electrically, or .
- 2) Hydraulically by closing the drive water and exhaust water isolation valves
*May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
**The inoperable control rod may then be withdrawn to a position no further dlawn than its position when found to be inoperable.
#See Special Test Exception 3 g LA SALLE - UNIT 2 3/4 1-3 Amendment No. 30
l 4'N 1 REACTIVITY CONTROL SYSTEM-CONTROL ROD MAXIMUM SCRAM INSERTION TIMES
't LIMITING CONDITION FOR OPERATION l
3.1.3.2 The maximum scram insertion time of each control rod from the fully withdrawn position to notch position 05, based on de-energization of the scram pilot' valve solenoids as time zero, shall not exceed 7 seconds. APPLICABILITY: OPERATIONAL CONDITIONS I and2h l ACTION:
- a. With the maximum r, cram insertion time of one or more control rods exceeding 7 seconds:
. , 1. . Declare the control rod (s) with the slow insertion time inoperable, and
- 2. Perform the Surveillance Requirements of Specification 4.1.3.2c.
at least once per 60 days when operation is continued with three or more control rods with maximum scram insertion times in excess of 7 seconds. Otherwise, be in at least HOT SHUTOOWN within 12 hours. 't -
- b. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during' single control rod scram time tests, the control rod drive pumps isolated from the accumulators: ,
- a. For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS
- cr after a reactor shutdown that is greater than 120 days,
- b. For specifically affected individual control rods following i
maintenance on or modification ta the control rod or control rod drive system which could affan the scram insertion time of those specific control rods,.and
- c. For at least 10% of the control rods, on a rotating basis, at least once per 120 days of operation.
"Except movement of SRM, IRM or special movable detectors or normal control red movement.
ee Special Test Exception 3 l 3/4 1-6 Amendment No. 30 LA SALLE - UNIT 2
A . REACTIVITY CONTROL SYSTEM-COMROL ROD AVERAGE SCRAM INSERTION TIMES
-LIMITING CONDITION FOR OPERATION 6 3.1.3.3 The average scram insertion time of all OPERABLE control rods fror
-the fully withdrawn position, based on de-energi2ation of.the scram pilot valve solenoids as time zero, shall not exceed any of the following:
Position Inserted From Average Scrat. Inser-Fully Withdrewn tien Time (Seconds) 45- 0.4? 39 0.86 25 1.93 05 3.49 APPLICABILITY: OPERA 110NALCONDITIONS1*and2h l ACTION:
-With the average scram insertion time exceeding any of the above limits, be in at,least HDT SHUTDOWN within 12 hours.
SURVEILLANCE REQUIREMENTS 4.1.3.3 All control rods shall be demonstrated OPERABLE by scram time testing from.the fully withdrawn position as required by Surveillance Requirement 4.3.3.2. v-
@eeSpecialTestException3.10.10 g LA SALLE - UNIT 2 3/4 1-7 Amendment No. 30
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REACTIVITY CONTROL SYSTEM l FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES q
'( l LIMITING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position,.
for the three fastest control rods in each group of four control rods arranged . in.a two-by-two array, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed any of the following: i Position Inserted From Average Scram Inser-Fully Withdrawn tion Time (Seconds) 45 0.45 39 0.92 25 2.05 05 3.70 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2D l ACTION:
.a. With the average scram insertion times of control rods exceeding the above limits:
.{ 1. Declare the control rods with the slower than average scram insertion times inoperable until an analysis is performed to determine that required scram reactivity remains'for the slow four control rod group, and
- 2. . . Perform the Surveillance Requirements of Specification 4.1.3.2c.
at least once per 60 days when operation is continued with an average scram insertion time (s) in excess of the average scrarg insertion time limit. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours.
- b. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2. ion 3.10. g
]SeeSpecialTestExc i
3/4 1-8 Amendment No. 30 LA SALLE.- UNIT 2
REACTIVITY CONTROL SYSTEM CONTROL ROD SCRAM ACCUMULATORS
-( LIMITING CONDITION FOR OPERATION' 3.1.3.5 All control . rod scram accumulators shall be OPERABLE.
. APPLICABILITY: OPERATIONAL CONDITIONS Y , 2 andSD l ACTION:
- a. In OPERATIONAL CONDITION 1 or 2: -
- 1. With one control rod scram accumulator inoperable: I a) Within 8 hours, either: I
- 1) Restore the inoperable accumulator to OPERABLE status,- j or
- 2) Declare the control rod associated with the inoperable l accumulator inoperable.
b) Otherwise, be in at least HOT SHUTDOWN within the next ! 12 hours. -l
- 2. With more than one control rod scram accumulator inoperable, declare the associated control rod inoperable and:
a) If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one CRD pump is operating by inserting at least'one with-drawn control rod at least one notch by drive water pressure within the normal operating range or place the reactor mode switch in the Shutdown position. ( b) Insert the inoperable control rods and disarm the associated directional control valves either:
- 1) Electrically, or
- 2) Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within 12 hours.
- b. In OPERATIONAL CONDITION 5 with:
- 1. One withdrawn control rod with its associated scram accumulator inoperable, insert the affected control rod and disarm the associated directional control valves within 1 hour, either:
a) Electrically, or b) Hydraulically by closing the drive water and exhaust water. 1 solation valves.
- 2. More than one withdrawn control rod with the associated scram accumulator inoperable or with no control rod drive pump operating, immediately place the reactor mode switch in the Shutdown position.
- c. The provisions of Specification 3.0.4 are not applicable.
"At least the accumulator associated with each withdrawn control rod. Not applit:ahle ta cantrol rods removed per Specification 3.9.10.1 or 3.9.10.2.
See Special Test Exception s l
.LA SALLE - UNIT 2 3/4 1-9 Amendment No. 30
l
- g. .,
l- . p' . . REACTIVITY CONTROL SYSTEM CONTROL ROD ORIVE COUPLING ( LIMITING CONDITION FOR OPERATION' ! 3.1.3.6 All control rods.shall be coupled to their drive mechanisms. APPLICABILITY: OPERATIONALCONDITIONS1D2Dand5* l l ACTION: I
- a. In OPERATIONAL CONDITIONS I and 2 with one control rod not coupled to its associated drive mechanism
- 1. Within 2 hours, either: (
a) If permitted by the RWM and RSCS, insert the control rod drive mechants to accomplish recoupling and verify recoupling by withdrawing the control rod, and: j
- 1) Observing any indicated response of the nuclear instrumentation, and
- 2) Demonstrating that the control rod will not go to the overtravel position. l b) If recoupling is not accomplished on the first attempt or, if not permitted by the RWM or RSCS then until permitted by the RWM and RSCS, declare the control rod inoperable and insert the control rod and disarm the associated directional control valves ** either:
{ 1) Electrically, or l
- 2) Hydraulically by closing the drive water and exhaust water isolation valves.
- 2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours,
- b. In OPEitATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours, either:
- 1. Insert the control rod to accomplish recoupling and verify .
recoupling by withdrawing the control rod and demonstrating .l that the control rod will not go to the overtravel position, or '
- 2. If recoupling is not accomplished, insert the control rod and disarm the associated directional control valves ** either:
a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.
- c. The provisions of Specification 3.0.4 are not applicable.
"At least each withdrawn control rod. Not applicable to control rods removed
~
per Specification 3.9.10.1 or 3.9.10.2.
**May be rearmed intermittently, under administrative control, to permit testing a HDCiated with restoring the control rod to OPERABLE status.
Special Test Exception g
. LA SALLE - UNIT 2 3/4 1-11 Amendment No. 30
lJ. . L REACTIVITY CONTROL'5YSTEM I CONTROL ROD POSITION INDICATION LIMITING CONDITION FOR OPERATION-
'3.1.3.7 The control rod position indication system shall be OPERABLE.
A ' APPtICADILITY: OPERATIONALCONDITIONSlb2 and 5*b ACTION:
- a. In OPERATIONAL CONDITION 1 or 2 with one or more control rod positio, indicators inoperable within one hour:
- 1. Determine the position of the control rod by:
(a) Moving the control rod, by single notch movement, to a position with an OPERABLE position indicator, ~t (b) Returning the control rod, by single notch movement, to its original position, and (c) Verifying no control rod drift alarm at least once per 12 hours, or
- 2. Move tne control rod to a position with an OPERABLE position inflicator, or
- 3. When THERMAL, POWER is:
(a) Within the low power setpoint of the RSCS: (1) Declare the control rod inoperable, (2) Verify the position and bypassing of control rod with inoperable " Full in" and/or " Full out" position indi-cators by a second licensed operator or other techni-cally qualified member of.the unit technical. staff. .i L) Greater than the low power setpoint of the RSC5, declare tne control rod inoperable, insert the control rod and disarm the associated directional control valves ** either: (1) Electrically, or . (2) Hydraulically by closing the drive water and exhaust water isolation valves.
- 4. Otherwise, be in at least HDT SHUTDOWN within the next 12 hours.
"At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 er 3.9.10.2.
**May be rearmed intermittently, under administrative control, to permit testing associated with rettering the rol rod to OPERABLE status.
Q5eeSpecialTestException3.10.10. i LA SALLE - UNIT 2 3/4 1-13 Amendment No. 30
I REACTIVITY CONTROL SYSTEM 3/4.1.4 CONTROL ROD PROGRAM CONTROLS k ROD WDRTH MINIMIZER LIMITING CONDITION FOR OPERATION 3.1.4.1 The rod worth minimizer (RWM) shall be OPERABLE. APPLICABILITY: OPERATIONAL' CONDITIONS 1 and 2* b en THERMAL POWER l' is less than or equal to 20% of RATED THERMAL POWER, the minimum allowable low power setpoint. ACTION:
- a. With the RWM inoperable, verify control rod movement and compliance with the prescribed control. rod pattern by a second licensed operator
,, or other technically qualified member of the unit technical staff
. who is present at the reactor control console. Otherwise, control rod movement may be only by actuating'the manual scram or placing the reactor mode switch in the Shutdown position.
- b. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
'4.1.4.1 The RWM shall be demonstrated OPERABLE:
- a. In OPERATIONAL CONDITION 2 prior to withdrawal of control rods for the purpose of making the reactor critical, and in OPERATIONAL CONDITION 1 prior to RWM automatic initiation when reducing THERMAL POWER, by verifying prepar annunciation of the selection error of at least one out-of-sequence control rod.
- b. In OPERATIONAL CONDITION 2 prior to withdrawal of control rods for-the purpose of making the reactor critical, by verifying the rod l l block function by demonstrating inability to withdraw an out-of . i sequence control rod. j
- c. In OPERATIONAL CONDITION'I within I hour after RWM automatic initiation when reducing THERMAL POWER, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence l
control rod.
- d. By verifying the control rod patterns and sequence input to the RWM computer is correctly loaded following any loading of the program into the computer.
" Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal of control rods for the purpose of bringing the reactor to criticality-cial Test Exception 3.10.8 g LA SALLE - UNIT 2 3/4 1-16 Amendment No. 30
p~ , 4 a
'l REACTIVITY CONTROL-SYSTEM ROD SEQUENCE CONTROL SYSTEM I
LIMITING CONDITION FOR OPERATION 3.1.4.2 The rod sequence control system (RSCS) shall be OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS I and 2* when THERMAL POWER is less l than or equal to 20% RATED THERMAL POWER, the minimum allownble low power setpoint. ACTION:
- a. With the RSCS inoperable:
- 1. Control rod withdraws 1 for reactor startup shall not begin.
- 2. Control rod movement shall not be permitted, except by a scram.
, b. - With an inoperable control rod (s), OPERABLE control rod movement may continue by bypassing the inoperable control rod (s) in the RSCS provided that:
- 1. The position and bypassing of inoperable control rods is verified by a second licensed operator or other technically qualified member of the unit technical staff, and i
- 2. There are not more than 3 inoperable control rods in any RSCS
( . group. SURVEILLANCE REQUIREMENTS 4.1.4.2 The RSCS'shall be demonstrated OPERABLE by:
- a. Performance of a self-test prior to:
- 1. Each reactor startup, and
- 2. Rod inhibit mode automatic initiation when reducing THERMAL -
POWER.
- b. Attempting to select and move an in'hibited control rod:
- 1. After withdrawal of the first insequence control rod for each reactor startup, and
- 2. Within one hour after rod inhibit mode automatic initiation when reducing THERMAL POWER.
"See Special Test Exception 3.10.2.
# Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RSCS prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(**SeeSpecialTestException3.1 l 1 LA SALLE - UNIT 2 3/4 1-17 Amendment No.30
-____-__-_____ -_____ _ D
3/4.9 REFUELING OPERATIONS
.3/4.9.1 REACTOR MODE SWITCH LIMITING CONDITION FOR OPERATION 3.9.1 The reactor mode switch shall be OPERABLE and' locked in the Shutdown or Refuel position. When the reactor mode switch is locked in the Refuel position:
- a. A control rod % er than 02- all not be withdrawn unless the M Refuel position one-rod-out interlock is OPERABLEf(and during the '
i _s 'eicono fuel cycle, contruLrod 02-43 is disarmea ano Tua ly inser e .
- b. CORE ALTERATIONS shall not be performed using equipment associated with a Refuel position interlock unless at least the following Refuel :
position interlocks are OPERABLE for such equipment. ;
- 1. All rods in. 1
- 2. Refuel platform position, i
- 3. Refuel platform hoists fuel-loaded.
- 4. Service platform hoist fuel-loaded.
APPLICABILITY: OPERATIONAL CONDITION 5*# . l i ACTION-
. a. With the reactor mode switch not locked in the Shutdown or Refuel position as specified, suspend CORE ALTERATIONS and lock the reactor mode switch in the Shutdown t.. 'uel position. !
- b. With the one-rod-out interlock inoperable, lock the reactor mode switch.in the Shutdown position. ;
3 i
- c. With any of the above required Refuel position equipment interlocks j
inoperable, suspend CORE ALTERATIONS with equipment associated with the inoperable Refuel position equipment hterlock. I
^ See Special Test Exceptions 3.10.1 and 3.10.3. "
#The reactor shall be maintained in OPERATIONAL CONDITION 5 whenever fuel is i in the reactor vessel with the vessel head closure bolts less than fully )
tensioned or with the head removed. l j H The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that all control j rods are verified to remain fully inserted by a second licensed operator or ! I other technically qualified member of the unit technicel staff. 1 LA SALLE - UNIT 2 3/4 9-1 Amendment No. 30 i
SP IAL TEST EXCEPTIONS ( /4.1 CONTROL ROD PROGRAM CONTROLS
\-
LIMITING CONDLTION FOR OPERATION t 3.10.8 The provisions f Specifications 3.1.4.1 and 3 .4.2 may be suspended for control rod 02-43 du gthesecondfuelcycletpallowthedemonstration of a fine. motion control drive installed at thi control rod location. The FMCRD 02-43 will be bypa ed in the Rod Sequen e Control System (RSCS) and ' programmed out of the Rod Wort Minimizer (RWM). APPLICABILITY: OPERATIONAL CONDIT NS1andp. ACTION: Movement of control rod 02-43 during the cond fuel cycle is permitted provided that:
- a. Thermal power is greater an 25% Rat Thermal Power, and 3
- b. A rod pattern has been stablished. l SURVEILLANCE REQUIREMENTS '
( 4.10.8 Prior to moveme of control rod 02-43 during the secon uel cycle, a second licensed opera or other technically qualified member of he unit technical staff who i present at the reactor control console will s rify that:
- a. Thermal wer is greater than 25% Rated Thermal Power, and
- b. Arod ttern has been established.
1 3/4 10-9 AMENDMENT NO. 30 LA SALLE - UNIT 2 i - _ _ - _ _ - _ - _ - _ _ _ _ _ _ _ -
\SPECIAL TEST EXCEPTIONS 3 4.10.9 SHUTDOWN MARGIN
( LIMI NG CONDITION FOR OPER4 TION / ) f 3.10.9 SHUTDOWN MARGIN is equal to or greater than:
- a. 0.3 delta k/k with the highest worth rod analytically determined, or
- b. 0.28% ' elta k/k with the highest worth rod dete ned by test. j (With a increased allowance fer the withdrawn ' orth of FMCRD 02-43.) !
APPLICABILITY: OPERAT ONAL CONDITIONS 1, 2, 3, 4, a 5. ACTION: f I' With the SHUTDOWN MARGIN less than specified:
\
In OPERATIONAL CONDITION 1 or 2, Reestablish the required SHUTDOWN 1 a. MARGIN within 6 hours or in t least HOT SHUTDOWN within the next l 12 hours. ,
- b. In OPERATIONAL CONDITION 3 or , immediately verify all insertable control rods to be insertep'and yuspend all activities that could reduce the SHilTDOWN MARGIK. In O'PERATIONAL CONDITION 4, establish .
SECONDARYCONTAINMENTIpTEGRITYWITyN8 hours.
- c. In OPERATIONAL CONDITIAN 5, suspend CDRE ALTERATIONS and other C activitiesthatcould'reducetheSHUTDbWNMARGIN,andinsertall insertable control r'ods within I hour. stablish SECONDARY CONTAINMENT INTEG ITY within 8 hours.
SURVEILLANCE REQUIREMENT , 4.10.9 The SHUTD0 MARGIN shall be determined with an inc ased allowance - for the withdrawn worth of the fine motion control rod 02-43 o be equal to or I edfiedatanytimeduringthesecondfuelcycl: greaterthansp/ \
- a. By measurement, prior to or during the first startup af er each refdeling.
- b. By measurement, within 500 MWD /T prior to the core averag exposure it which the predicted SHUTDOWN MARGIN, including uncertai ies and calculation biases, is equal to the specified limit.
c Within12hoursafter'detectionofawithdrawncontrolrodth(is immovable, as a result of excessive friction or mechanical intet-ference, or is untrippable, except that the above required SHUTDDWN MARGIN shall be verified acceptable with an increased allowance ihr the withdrawn worth of the immovable or untrippable control rod.
#Except movement of IRMs, SRMs or specia'l moveable detectors. ,
3/4 10-10 Amendment No. 30 LA SALLE - UNIT 2
t SEECIAL TEST EXCEPTIONS :
' 3 /4 0.10 CONTROL RODS LIMIT]NG OITION FOP OPERATION /
l 3.10.10 The pros'sions of Specifications 3.1. thru 3.1.3.7 may be suspended for control rod 02 3'during the second fuel ycle to allow the demonstration of a fine motion con 01 rod crive installe# at this control rod location, provided conditiers of S.10.9 are satisf' d. ' APPLICAE!LITi: CPERAi!CNI.L OCIT1048 1, 2, and 5. A',T 10N : With the recuiren.ents of .10. snot satisfied, immediately insert contrci l roc 02-43 and disare lie drive motor electrically I SURLEILLAN:E RECD EvEMS 4.10.10 Th provisions of Specification 4.1.3.1 thru 4. 3.7 may be suspended for contr rod 02-43 during the second fuel cycle to allo the demonstration of a fip metion control rod drive installed at this locatio l 1 i i i l i' OL LA sat.LE - UNIT 2 3/4 10-11 Amere ent No. 30
1 1 . REACTIVITY' CONTROL SYSTEMS SPECIAL-TEST EXCEPTIONS BASES \ 3/4.10.8 CON SOL ROD PROGRAM CONTROLS With the in plant demonstration of a fine motion control rod d ve (FMCRO) installed at the pe ipheral location 02-43 during the second uel cycle, position 02-43 will bypassed in the Rod Sequence Control ystem (RSCS) and progr6 :med out of the Worth Minimizer (RWM). This wil free the FMCRD rod j from-the Banked Positio ithdrawal Sequence (BPWS) and tch movement restrictions. By requiri R that thermal power be great r than 25% rated l rn be established (after he withdrawal / insert l thermal sequencespower and aPosi of its Banked rod patt(tion Withdrawal Sequenceroup are complete) before movement of control rod D-43, one ensures at this rod will be moved o.nly under conditions when the R$$5 and EWM are n required to be operable. Af ter one Cycle of demonstration 4th this cont I rod, position 02-43 will be returned to the RSCS and RWM in conjunction wit the reinstallation of the original locking piston control rod. 3/4.10.9 SHUTDOWN MARGIN With the in plant demonstration of a 'ne mption control rod drive installed ! at 02-43 during the second fuel cycl the s utdown margin shall be demonstrated l assuming this control rod is at the ully wit drawn position. In other vords, i during the second fuel cycle, the hutdown mar in shall be equal to or greater s e ification 3.1.1 with the most reactive control ! than rod and thethe values specified fine motion controin Sp/ rod fully withdra n. , 3/4.10.10 CONTROL ROD A fine motion control r. drive will be installed at L Salle County Station Unit-2 during the set fuel cycle. To minimize the s .ety impact, a peri- ; pheral location 02-4 is selected. Due to the temporary est nature of this ' control rod drive, y fety evaluation has been performed t justify continued safe operation of Ahe reactor assuming this control rod dr e is inoperable.
. However, this to is not considered inoperable in the contex of specifications 3.1.3.1 throug 3.1.3.7 and any scram time will 'not be includ d in 1,y, in specificati 3/4.2.3. Thus during the second fuel cycle opera ion the LCO and surveillan requirements applicable to regular control rods are xempted for this cont I rod. After one cycle of demonstration, this control od drive will be emoved and the original locking piston control rod drive 'll be reins led at this location.
I, i LA SALLE - UNIT 2 B 3/4 10-2 Amendment No. 30
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k) ' INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION .
.PAGE W 4.10 SPECIAL T_EST EXCEPTIONS (Continued) 3/4.10.8 o1 Rod Program Controls......... m c ......... 3/4 10-9
/
3/4.10.9' Shutdown Marg . ...................................... 3/4 10-10 nt.rol Rods .................. ......................... 3/4 10-11
,, r .- %
I ' 3/4.11 RADI0 ACTIVE EFFLUENTS #I l 3/4.11.1 LIQUID EFFLUENTS l 3 gg Concentration................................................ 3/4 n-1 j 3/4 11-6' Dose......................................................... Liquid Waste Treatment System................................ 3/4 11-7 Li q ui d Hol dup Tan ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-8 3/4 11.2 GASEOUS EFFLUENTS Dose Rate.................................................... 3/4 11-9 j i Dose-Noble Gases............................................. 3/4 11-13 i Dose-Radiciodines, Radioactive Material in Particulate j Form, and Radionuclides Other than Noble Gases............. 3/4 11-14 j Gaseous-Waste Treatment System............................... 3/4 11-15 'h 1 VentijationExhaustTreatmentSystem......................... 3/4 11-16 ] Explosive Gas Mixture........................................ 3/4 11-17 Main Condenser............................................... 3/4 18 , t Venting or Purging........................................... 3/4 11-19 < 3/4 11.3 SOLID RADI0 ACTIVE WASTE...................................... 3/4 11-20 3/4 11.4 TOTAL D0SE................................................... 3/4 11-22 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING > 1 s l j 3/4 12.1 MONITORING PR0 GRAM........................................... 3/4 12-1 ; , 3/4 12.2 LAND USE CENSUS.............................................. 3/4 12-9 f 3/4 12.3 INTERLABORATORY COMPARISON PR0 GRAM........................... 3/4 12-10 LA SALLE - UNIT 2 XI Amendment No. 30 t i}}