ML19354D700

Proposed Tech Specs,Clarifying General Requirements for Application to Limiting Conditions for Operations & Surveillance Requirements

ML19354D700
Person / Time
Site:	LaSalle
Issue date:	12/15/1989
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19354D698	List: ML19354D697 ML19354D700
References
NUDOCS 8912290126
Download: ML19354D700 (100)

Text

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3/4.0~ APPLICABILITY  ;

LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other '

conditions specified therein; except that upon failure to meet the Limiting

-Conditions for Operation, the associated ACTION requirements shall be met.

-3.0.2 . Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required, h 3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

1. At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION L

requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the indiv'idual Specifications.

This specification is not applicable in OPERATIONAL CONDITION 4 or 5. f 3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made unless the conditions for the Limiting Condition for Operation are i met without reliance on provisions contained in the ACTION requirements. This provision-shall not prevent passage through OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications. -

hR t 3.0.5 When a system, subsystem, train, component or device is determined to lgY be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered 1- A OPERABLE.for the purpose of satisfying the requirements of its applicable limiting condition for Operation provided: (1) its corresponding normal or emergency power source is CPERABLE; and (2) all of its redundant system (s),

subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in:

1. At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This specification is not applicable in OPERATIONAL CONDITION 4 or 5.

LA SALLE - UNIT 1 3/4 0-1 8912290126 891215 PDR ADOCK 05000373

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L APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements snall be met during the OPERATIONAL CONDITIONS j or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirements.

4.0.2 Each Surveillance Requirement shall be performed within the specified

1. 4 surveillance 25 percentinterval with a maximum of the specified allowable surveillance extension not to exceed interval.

9 4.0.3 Failure to perform a Surveillance Requirement within the specified t  !

interval shall constitute a failure to meet the OPERABILITY requirements for a '

W3 Limiting Condition for Operation. Exceptions to these requirements are stated ,

in the individual Specifications. Surveillance requirements do not have to be /

performed on inoperable equipment. j 4.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall  ;

not be made unless the Surveillance Requirement (s) associated with the Limiting '

Condition for Operation have been performed within the stated surveillance

• I interval or as otherwise specified. )'

O k.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (i),

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days LA SALLE - UNIT 1 3/4 0-2 AMENDMENT NO.68

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1 REACTIVITY CONTROL SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

! 2. 'If the inoperable control rod (s) is inserted: -

J l- i l a) Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> disarm the associated directional control. lS valves

• either:

1) Electrically, or  !

2) Hydraulically by closing the drive water and exhaust water isolation valves.

b) Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. _

[3. The provisions of Specification 3.0.4 are not applicable. ls I c. With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i SURVEILLANCE REQUIREMENTS ,

l i 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

a. - At least once per 31 days verifying each valve to be open**, and

. l i8 At least once per 92 days cycling each valve through at least one

~

b.

complete cycle of full travel.

4.1.3.1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required tot have their directional control valves disarmed electrically 'or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:

a. At least once per 7 days, and

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is innovable as a result of exct ssive friction or mechanical interference.

4.1.3.1.3 All control rods shall be demonstrated OPERA 8LE by performance of Surveillance Requirements 4.1.3.2, 4.1.3.4, 4.1.3.5, 4.1.3.6 and 4.1.3.7.

• May be rearmed intermittently, under administrative control, to permit testing l is associated with restoring the control rod to OPERABLE status.

• • These valves may be closed intermittently for testing under administrative l is control.

LA SALLE - UNIT 1 3/4 1-4 Amendment No. 18

t REACTIVITY CONTROL SYSTEM'

' CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 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-energi2ation of the scram pilot valve solenoids as time zero, shall not exceed 7.0 seconds. '

' APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

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[

l ACTION: ,

al With the maximum scram insertion time of one or more control rods

,,g, exceeding 7.0 seconds:

L L

1. Declare the control rod (s) with the slow insertion time inoper-able, and

2. Perform the Surveillance Requirements of Specification 4.1.3.2.c l at.least once per 60 days when operation is continued with l ,, three or more control rods with maximum scram insertion times p in excess of 7.0 seconds.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(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 roos 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 l THERMAL POWER following CORE ALTERATIONS ** or after a reactor shutdown i that is greater than 120 days,

b. For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect 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 ccatrol rod movement.

LA SALLE - UNIT 1 3/4 1-6 Amendment No. 58 l

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REACTIVITY CONTROL SYSTEM FOUR CONTROL R00 GROUP SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position, for the three fastest contro1~ 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:

L Position Inserted Fronr 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 2.

! ACTION:

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 e 2. Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with an L average scram insertion time (s) in excess of the average scram j insertion time limit.

,0therwise, be in at least HOT-SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(b The provisions of Specification 3.0.4 are not applicabl 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.

LA SALLE - UNIT 1 3/4 1-8 Amendment No. 58

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REACTIVITY CONTROL SYSTEM CONTROL R0D SCRAM ACCUMULATORS LIMITING CONDITION 70R OPERATION .

3.1.3.5 All control rod scram accumulators shall be OPERABLE.

APPLICABILITY:. OPERATIONAL CONDITIONS 1, 2 and 5*. .

ACTION:

i a. In OPERATIONAL CONDITION 1 or 2:

1. With one control rod scram accumulator inoperable:

a) Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either:

1) Restore the inoperable accumulator to OPERABLE status, or

2) Declare the control rod associated with the inoperable accumulator inoperable.

b) Otherwise, be in at least HOT SHUTOOWN within the next

h. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

With more than one control rod scram accumulator inoperable,

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2.

- 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 e.'haust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. In OPERATIONAL CONDITION 5 with:

1. One withdrawn control rod with its associated scram accumlator inoperable, insert the affected control rod and disarm the associated directional control valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either: l a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

b 2. More than one withdrawn control rod with the associated scram accumulator inoperable or with no control rod drive pump f'

operating, innediately place the reactor mode switch in the Shutdown position.

I The provisions of Specification 3.0.4 are not applicable.

h. l

• At least the accumulator associated with each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. l LA SALLE - UNIT 1 3/4 1-9 Amendment No. 18

REACTIVITY CONTROL SYSTEM' CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*.

ACTION:

a. In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled to its associated drive mechanism:

1. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

a) If permitted by the RWM and RSCS, insert the control rod drive mecharfism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

1) Observing any indicated response of the nuclear instrumentation, and

2) Demonstrating that the control rod will not go to the overtravel position, 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

2) Hydraulically by closing the drive water and exhaust water isolation valves.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

1. Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating 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.

h The provisions of Specification 3.0.4 are not applica

• 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 associated with restoring the control rod to OPERABLE status.

LA SALLE - UNIT 1 3/4 1-11 Amendment No. 58

4 REACTIVITY CONTROL SYSTEM.

LIMITING CONDITION FOR OPERATION (Continued)-

ACTION (Continued)

b. In OPERATIONAL CONDITION 5" with a withdrawn control rod position  ;

indicator inoperable, move the control rod to a position with an OPERABLE position indicator or insert the control rod.

(c. The provisions of 3.0.4 are not applicab SURVEILLANCE REQUIREMENTS 4.1.3.7 The control rod position indication system shall be determined OPERABLE

- by verifying:

$. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the position of each control rod is indicated,

b. That the indicated control rod position changes during the movement of the control rod drive when performing Surveillance Requirement I-4.1.3.1.2, and

c. That the control rod position indicator corresponds to the control rod position indicated by the " Full out" position indicator when '

performing Surveillance Requirement 4.1.3.6b.

d. . That the control rod position indicator corresponds to the control rod position indicated by the " Full in" position indicator:

1. Prior to each reactor startup, and ,

2 Each time a control rod is fully inserted.

o

.I i

- "At least each withdrawn control rod not applicable to control rods removed per Specifications 3.9.10.1 or 3.9.10.2.

LA SALLE - UNIT 1 3/4 1-14 Amendment No. 26

REACTIVITY CONTROL SYSTEM 3/4.1.4 CONTROL-ROD PROGRAM CONTROLS R0D WORTH MINIMIZER LIMITING CONDITION FOR OPERATION 3.1.4.1 The rod worth minimizer (RWM) shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*, when THERMAL POWER 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.

The provisions of Specification 3.0.4 are not applicable (b.

l 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 reaching 20% of RATED THERMAL POWER when reducing THERMAL POWER, by verifying proper 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 block function by demonstrating inability to withdraw an out-of-l sequence control rod,

c. In OPERATIONAL CONDITION 1 within one hour after RWM automatic initiation when reducing THERMAL POWER, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence 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.

LA SALLE - UNIT 1 3/4 1-16 Amendment No. 58

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEN INSTRUMENTATION LINITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

At'. h4

a. With the number of 0PERA8LE channels less than required by the Minimum

• OPERA 8LE Channels per Trip Systes requirement for one trip system, place the inoperable channels and/or trio system in the triaaad enaMttan* ,

j within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Qhe prov'sions of Specification 3.0.4 are not applicable.

h. With the the number of CPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Systes requirement for both trip systen.s, place at least one trip systes** in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIRENENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1 1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic o all channels shall be performed at least once per 18 months;*** peration of 4.343 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per trip systes such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.

m With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the noperable channel shall be restored to OPERA 8LE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ION required by Table 3.3.1-1

=for that Trip Function shall be taken.

en If more channels are inoperable in one trip system than in the other, select that trip system to place in the tripped condition, except when';this would cause the Trip Function to occur.

• • • The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1, which is to commence no later than October 27, 1985.

LA SALLE - UNIT 1 3/4 3-1 Amendment No. 30

1 INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION ,

LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 c shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3. ,

. APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. With the number of OPERABLE channels less than required by the Mini-mum OPERABLE Channels per Trip System requirement for one trip system, l place the operable channel (s) and/or trip system in the tripped con-dition*withinonehour.(TheprovisionsofSpecification3.0.~4are ~

notapplicable)

c. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition *** l within one hour and take the ACTION required by Table 3.3.2-1.

• An inoperable channel need nnt be placed in the tripped condition where this l would cause the Trip Function to occur. In these cases, the inoperable channel

_ shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by by Table 3.3.2-1 for that Trip Function shall be taken.

• • If more channels are inoperable in one trip system than in the other, select that trip system to place in the tripped condition except when th'is would cause the Trip Function to occur.

• • • An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

LA SALLE UNIT-1 3/4 3-9 Amendment No. 26

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TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

~

ACTION ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERA 8LE Channels per Trip Function requirement:

s. With one channel _-inoperable, place the inoperable channel-in the tripped condition within one hour

• or declare the^

associated system inoperable,

b. With more than one channel inoperable, declare the associated system inoperable.

l ACTION 31 - With the number of OPERABLE channels less than required by the i Minimum OPERABLE channels per Trip Function, place the inoperable channel-in the tripped condition within one hour; restore the inoperable channel to OPERABLE status within 7 days or declare

, the associated system inoperable.

ACTION 32 - WP a the number of OPERABLE channels less than required by i

tne Minimum OPERABLE Channels per Trip Function requirement,

, declare the associated ADS trip system or ECCS inoperable.

L ACTION 33 - With the number of OPERABLE channels less than the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

L ACTION 34 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ADS trip system or ECCS inoperable.

ACTION 35 - With the number of OPERABLE channels less.than required by the Minimum OPERA 8LE Channels per Trip Function requirement

a. For one trip system, plac at trip system in the tripped condition within one ho

• or declare the HPCS system inoperable.

b. For both trip systems, declare the HPCS system inoperable.

ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OP BLE Channels per Trip Function req 0irement, place at . leas inoperable channel in the tripped condition within one hou or declare the HPCS system inoperable.

ACTION 37 - With the number of OPERABLE instr s less than the Minimum l Operable Instruments, place the operable instrument (s) in the tripped condition within l' hou

• or declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as appropriate.

provisions of Specification 3.0.4 are not applicable

LA SALLE - UNIT 1 3/4 3-27 Amendment No. 41 1

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INSTRUMsNTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION

1. Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Limiting Condition for Operation (LCO) to the EOC-RPT inoperable value per Specifica-tion 3.2.3 within the next I hour or,

2. reduce THERMAL POWER to less than 30% of RATED THERMAL POWER withis the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

h The provisions of Specification 3.0.4 are not applicabl SURVEILLANCE REQUIREMENTS 4.3.4.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by-the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.2.1-1.

4.3.4.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

o 4.3.4.2.3~ The END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of

each trip function shown in Table 3.3.4.2-3 shall be. demonstrated to be within l its limit at least once per 18 months. Each test'shall include at least the logic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested  ;

at least once per 36 months. The time allotted for breaker are suppression shall be verified by test at least once per 60 months.

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1 LA SALLE - UNIT 1 3/4 3-40 Amendment No. 58

INSTRUMENTATION' t 3/4.3.7 MONITORING INSTRUMENTATION v

RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE

• with their alarm / trip setpoints within the .

specified limits..

APPLICABILITY: As shown in Table 3.3.7.1-1.

ACTION:

a. With a radiation monitoring instrumentation channel alarm / trip

-setpoint exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

b. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1. .

The provisions of Specificatio

c. 0.3 e not applicable, v

. SURVEILLANCE REQUIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation

, channels shall be demonstrated OPERABLE by the performance of the CHANNEL l CHECK, CHANNEL. FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the

! conditions and at the frequencies shown in Table 4.3.7.1-1.

l-1' .

l "The normal or emergency power source may be inoperable in OPERATIONAL l CONDITION 4 or 5 or when defueled.

l' l

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LA SALLE - UNIT 1 3/4 3-56

i v.

INSTRUMENTATION

., ., SEISMIC MONITORING INSTRUMENTATION

• LIMITING CONDITION FOR OPERATION

3. 3. 7'. 2 The beOPERABLE.geisuicmonitoringinstrumentationshowninTable3.3.7.2-1shall APPLICABILITY: At all times.

ACTION:

a. With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission l

pursuant to Specification 6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status,

b. The provisions of Specificatio 0.3 and .0.4 re not applicable.

SURVEILLANCE REQUIREMENTS

~4.'3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL l _, TEST, and CHANNEL _ CALIBRATION operations at the frequencies shown in Table l 4.3.7.2-1. -

l 4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.029 shall be restored to u -

OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within

!. 5 days following the seismic event. Data shall be retrieved from actuated l- . instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission L

l pursuant to Specification 6.6.C within 10 days describing the magnitude,

, frequency spectrum and resultant effect upon unit features important to safety.

i

+ *The Seismic Monitoring Instrumentation System is shared between La Salle Unit I and La Salle Unit 2.

• • The normal or emergency power source may be inoperable in OPERATIONAL CONDlTION 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 3-60 Amendment No.23

p u

INSTRUMENTATION

, ,, METEOROLOGICAL MONITORING INSTRUMENTATION

• LIMITING CONDITION FOR OPERATION 3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.**

APPLICABILITY: At all times.

ACTION:

a. With one or more meteorological monitoring instrumentation channels inoperable for more than 7 days, prepare and submit a Special Report l to the Commission pdrsuant to Specification 6.6.C within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status, o-

b. The provisions of Specificatior@p3.0.3{d3.0Jarenotapplicable.

SURVE1LLANCE REQUIREMENTS ,

4.3;7.3 Each of the above required meteorological monitoring instrumentation channels shall.be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

s

• The Meteorological Monitoring Instrumentation System is shared between La Salle Unit 1 and La Salle Unit 2.

• • The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

i i

1

, LA SALLE - UNIT 1 3/4 3-63 Amendment No.23 1

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l INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7. The traversing in-core probe (TIP) system shall be OPERABLE with: ,

a. Movable detectors, drives and readout equipment to map the core in the required measurement locations and o

b. Indexing equipment to allow all required detectors to be calibrated in a common location. 1 APPLICABILITY: _ When the traversing in-core probe is used for:

• a. Recalibration of the LPRM detectors, and

• b. Monitoring the APLHGR, LHGR, MCPR, or MFLPD.

l ACTION:

a. With one or more TIP measurement locations inoperable, required measure-ments may be performed as described in 1 and 2 below, provided the Mactor core is operating in an octant symmetric control rod pattern, and the j total core TIP uncertainty for the present cycle has been measured to be l less than 8.7 percent.

1. TIP data for an inoperable measurement location may be replaced by data obtained from that string's redundant (symmetric) counterpart if the substitute TIP data was obtained from an operable measurement ,

location. l

2. TIP data for an inoperable measurement location may be replaced by l data obtained from a 3-dimensional BWR core simulator code aarmalized with available operating measurements, provided the total number of f simulated channels (measurement locations) does not exceed: l

. a) All channels of a single TIP machine, or b) A total of five channels if more than one TIP machine is involved.

b. 'Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable monitoring r. calibration functions.

c .- The provisions of Specificatio s 3.0.3 nd 3.0.4 re not applicable. l l

SURVEILLANCE REQUIREMENTS ]

-4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by J normalizing each of the above required detector outputs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to use for the above applicable monitoring or calibration functions.

"Only the detector (s) in the required measurement location (s) cre required to be OPERABLE.

LA SALLE - UNIT 1 3/4 3-73 Amendment No. 53 l

l l

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION

'3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone of Unit I and Unit 2 shown in Table 3.3.7.9-1 shall be OPERABLE.*

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instruments less than the Minimum Instruments OPERABLE requirement of Table 3.3.7.9-1:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, establish a fire watch patrol to inspect the zone (s) uith the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the primary containment, then inspect the primary containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.7.

b. Restore the minimum number of instruments to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l pursuant to Specification 6.6.C within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status, 0,

c. The provisions of Specifica,tio@p3.0.3 {d 3.0.4) ire not applicable.

SURVEILLANCE REOUIREMENTS 4.3.7.9.1 Each of the above required fire detection instruments which are accessible during unit openation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operatioh shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the polevious 6 months.,

d 4.3.7.9.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. Super-vised circuits with detectors which are inassessible during unit operation shall be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

t 9 he normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 3-75 Amendment No. 23

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints-set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm trip setpoints of these channels shall be determined in accordance with the Offsite Dose Calculation Manual (00CM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, in lieu of a Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified, h

c. The provisions of Specificatio 3.0.3kd3.0.4/arenotapplicable.

SURVEILLANCE REQUIREMENTS l

l t

4.3.7.10, Each radioactive liquid effluent menitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Ta,ble 4.3.7.10-1. .

LA SALLE - UNIT 1 3/4 3-81 Amendment No.18

INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ,

LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpuints of these channels shall be determined in accordance with the ODCM.

APPLICABILITY: As shown in Table 3.3.7.11-1 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive gaseous effluents -

monitored by the affected channel or declare the channel inoperable,

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

( The provisions of Specifications 3.0.3 and 3.0.4 are not applicable s

%./

SURVEILLANCE REQUIREMENTS 4.3.7.11~'Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.11-1. ,

v LA SALLE - UNIT 1 3/4 3-86

1 INST RUMENT AT,1,0N LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION o

3.3.7.12 The loose part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With one or more loose-part detection system channels inoperable for more than 30 days, prepare and submit a Sp: rial Report to the Commission pursuant to Specification 6.6.c within the next 10 days outlining the cause of the malfunction ?nd the plans for restoring the channel (s) to OPERABLE status.

( The provisions of Specifications 3.0.3 and 3.0.A are not applicabi SURVEILLANCE REQUIREMENTS 4.3.7.1:t Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of:

a. CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. CHANNEL FUNCTI0tiAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

LA SALLE - UNIT 1 3/4 3-91

l

^

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS LINITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant system recirculation loops shall be in operation.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 ACTION

a. With only one (1) reactor coolant system recirculation loop in operation, comply with Specification 3.4.1.5 and:

1

1. Within four (4) hours:

I a) Place the recirculation flow control system in the Master i Manual mode or lower, and j i

b) Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit by 0.01 to 1.08 per Specification 2.1.2, and d Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Limiting Condition for Operation by 0.01 per Specification 3.2.3, I and, l d) Reduce the Average Power Range Monitor (APRM) Scram and

' Rod Block and Rod Block Monitor Trip Setpoints and Allowable Values to those applicable to single i recirculation loop operation per Specifications 2.2.1, 3.2.2, and 3.3.6. )

The provisions of Specification 3.0.4 are not applicabl (2.

2[ Otherwise, be in at least HOT SHU' XNN within the next twelve (12) Nurs.

b. With no reactor coolant recirculation loops in operation:

1. Take the ACTION required by Specification 3.4.1.5, and l l l l 2. Be in at least HOT SHUTDOWN within the next six (6) hours. l l

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l l i LA SALLE - UNIT 1 3/4 4-1 Amendment No. 60 i

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,[A SALLE - UNIT 1 3/4 4-lb Amendment No. 60

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY .g LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY: At all times.

ACTION:

a. In OPERATIONAL CONDITION 1:

1. With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval and, for conductivity and chloride concentra-tion, for'less than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, but with the conductivity less than 10 pmho/cm at 25'C and with the chloride concentration less than 0.5 com this need not be reoorted to the Commissio an the provisions of Specification 3.0.4 are not applicab

2. With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval or, for conductivity and chloride concentra-tion, for more than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3. With the conductivity exceeding 10 pmho/cm at 25'C or chloride l- concentration exceeding 0.5 ppm, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN as rapidly as the cooldown rate limit L permits.

b. In OPERATIONAL CONDITION 2 and 3 with the conductivity, chloride concentra-tion or pH exceeding the limit specified in Table 3.4.4-1 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l

c. -At all other times:

1. With the conductivity or pH exceeding the limit specified in Table l 3.4.4-1, restore the conductivity and pH to within the limit within l- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2. With the chloride concentration exceeding the limit specified in i

Table 3.4.4-1 exceeded for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolant system remains acceptable for continued operation prior to proceeding to OPERATIONAL CONDITION 3.

3. The provisions of Specification 3.0.3 are not applicable. _

LA SALLE - UNIT 1 3/4 4-10

f REACTOR COOLANT SYSTEM 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.7 Two main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to 3 and less than or equal to 5 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With one or more MSIVs inoperable:

i 1. Maintain at least one MSIV OPERABLE in each affected main steam line that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:

a) Restore the inoperable valve (s) to OPERABLE status, or l b) Isolate the affected main steam line by use of a deactivated MSIV in the closed position, k2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and

) in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1

4.4.7 Each of the above required MSIVs shall be demonstrated OPERABLE by verifying full closure between 3 and 5 seconds when tested pursuant to Specification 4.0.5.

l l

l LA SALLE - UNIT 1 3/4 4-21

l REACTOR COOLANT SYSTEM '

3/4.4.8 STRUCTURAL INTEGRITY a

LIMITING CONDITION FOR OPERATION ,

3.4.8 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5. .

ACTION:

a. With the structural integrity of any ASME Code Class I component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations,

b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component ('s) to within its limit or ,

isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F.

t

c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural v integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

The provisions of Specification 3.0.4 are not applicable SURVEILLANCE REQUIREMENTS 4.4.8 No additional Surveillance Requirements other than those required by Specification 4.0.5.

v LA SALLE - UNIT 1 3/4 4-22

l CONTAINMENT SYSTEMS

• M IMARY CONTAINMENT 4!R LOCKS -

. l

. i LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERA 8LE with:

a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one i air lock door shall be closed, and i

b. '

An overall 39.6 psig. air lock leakage rate of less than or equal to 0.05 L, at P,,

APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.

l ACTION:

a. With one primary containment air lock door inoperable:

1. Maintain at least the OPERA 8LE air lock door closed and either restore the inoperable air lock door to OPERABLE status within l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERA 8LE air lock door closed.

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERA 8LE air lock l door is verified to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and '

in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

h. _

The provisions of Specification 3.0.4 are not applicable.

b. With the primary containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERA 8LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l I

• See Special Test Exception 3.10.1.

LA SALLE - UNIT 1 3/4 6-5 Amendment No. 18 l

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l

_ CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The primary containment isolation valves and the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With one or more of the primary containment isolation valves shown in Table 3.6.3-1 inoperable:

1.

Maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either; a) Restore the inoperable valve (s) to OPERABLE status, or b) Isolate each affected penetration by use of at least one pnsition,* orautomatic valve secured in the isolated deactivated c) Isolate each affected penetration by use of at least one closed manual valve or blind flange."

[d) The provisions of Specification 3.0.4 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the affected penetration is i isolated in accordance with Action a.1.b) or a.1.c) above, I and provided that the associated system is declared inoper- /

able, if applicable, and the appropriate action statements for that system are performed.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

, b.

- With one or more of the reactor instrumentation line excess flow check valves sh,own in Table 3.6.3-1 inoperable:

1. Ooeration y continue'and the provisions of Specifications 3.0.3 (and 3.0.4 not applicable.provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either: /

a) The inoperable valve is returned to OPERABLE status, or b) The instrument line is isolated and the associated instrument is declared inoperable.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i

^ Isolation valves closed to satify these requirements may be reopened on an intermittent basis under administrative control.

LA SALLE - UNIT 1 3/4 6-22 Amendment No. 26

PLANT SYSTEMS 3/4.7.4 SEALE0 SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.4 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 micro-curies of removable contamination.

APPLICABILITY: At all times.

ACTION:

a. With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with Commission Regulations.

DL

b. The provisions of Specificatio .0.3 0.4/arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.4.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.4.2 Test Frequencies - Each category of sealed sources, excluding startup l sources and fission detectors previously subjected to core flux, shall be tested at the frequency described below,

a. Sources in use - At least once per six months for all sealed sources containing radioactive material:

1. With a half-life greater than 30 days, excluding Hydrogen 3, and

2. In any form other than gas.

LA SALLE - UNIT 1 3/4 7-9

. PLANT SYSTEMS 3/4.7.5 FIRE SUPPRESSION SYSTEMS -

FIRE SUPPRESSION WATER SYSTEM LIMIT]NG CONDITION FOR OPERAT]ON 3.7.5.1 The fire suppression water system shall be OPERABLE

• with:

a. Two OPERABLE fire suppression diesel driven fire pumps, each with a capacity of 2500 ppm, with their discharce a14cned to the fire . . _ y suppression header,

b. An OPERABLE flow path capable of taking suction from the CSCS water tunnel and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler, hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.5.2 and 3.7.5.4.

APPLICABILITY: At all times.

ACTION:

a. With one fire pump and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or, prepare and submit a Special Report to the Commission pursuant to Specification l 6.6.C within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an a ate backun nom r supply. The provisions of Specificatio 3.0.3Qnd3.0.4 re not applicable.

b. With the fire suppression water system otherwise inoperable:

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and

2. Prepare and submit a Special Report in accordance with Specification 6.6.C; I a) By telsphone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b) Confirmed by telegraph, mailgram or facsilnile transmission no later than the first working day following the event, and c) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

• lhe normal or emer'gency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

J LA SALLE - UNIT 1 3/4 7-11 Amendment No.23 w

L

. PLANT SYSTEMS DELUGE AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.2 The deluge and sprinkler systems of Unit I and Unit 2 shown in Table 3.7.5.2-1 shall be OPERABLE.*

APPLICABILITY: Whenever equipment protected by the deluge / sprinkler systems are requireo to be OPERABLE.

ACTION: *

a. With one or more of the deluge and/or sprinkler systems shown in Table 3.7.5.2-1 inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within the l next 30 days outlining the action taken, the cause of the inoperabi-lity and the plans and schedule for restoring the system to OPERABLE status,

b. TheprovisionsofSpecification3.0.3hd3.0.hrenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.5.2 Each of the above required deluge and sprinkler systems shown in Table 3.7.5.2-1 shall be demonstrated'0PERABLE:

a. At least once per 31 days by verifying that each valve, (manual, power operated or automatic), in the flow path is in its correct position.

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel,

c. At least once per 18 months:

1. By performing a system functional test which includes simulated automatic actuation of the system, and:

a) Verifying that the automatic valves in the flow path actuate to their correct positions on a test signal, and b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

• The normal or emergency power source may be inoperable in OPERATIONAL CONDITJON 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 7-14 Amendment No. 23

i PLANT SYSTEMS CO2 SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO 2 systems of Unit I and Unit 2 shall be OPERABLE.*

a. Division I diesel generator 0 room.

b. Division 2 diesel generator IA room.

" ~ ~ ~ "

c. Division 3 diesel generator 1B room.

d. Unit 2 Division 2 diesel generator 2A room.

APPLICABILITY: Whenever equipment protected by the low pressure CO2 systems is required to be OPERABLE. ,

ACTION:

a. With one or more of the above required low pressure CO 2 systems inoperable, within I hbur establish a continuous fire watch with backup fire suppression equipment for those arean'in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, prepare and submit a Special Report to the Com-mission pursuant to Specification 6.6.C within the next 30 days l outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status,

b. The provisions of Specification 3.0.3 and e not applicable.

~

SURVEILLANCE REQUIREMENTS .

4.7.5.3 Each of the above required low pressure CO2 systems shall be demonstrated OPERABLE:

~

a. At least once per 7 days by verifying CO2 storage tank level to be greater than 50% full and pressure to be greater than 290 psig, and

b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in the , correct position,

c. At least once per IB months by verifying:

1

_ 1. The system valves and associated motor operated ventilation l- dampers actuate, manually and automatically, upon receipt'of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test."

l ^1he normal or emergency power source may be inoperable in OPERATIONAL  !

CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 7-17 Amendment No. 23

PLANT SYSTEM 5 FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION __

3.7.5.4 The fire hose stations of Unit I and Unit 2 shown in Table 3.7.5.4-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

~

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7.5.4-1 inoperable, route an additional fire hose of equal or greater diameter i to the unprotected area (s)/ zone (s) from an OPERABLE hose station within I hour if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore the inoperable fire hose station (s) to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l l pursuant to Specification 6.6.C within the next 30 days outlining the l action taken, the cause of the inoperability and the plans and I schedule for restoring the system to OPERABLE status.

)- .,

b. The provisions of Specificatio 3.0.3Qd3.0.4}renotapplicable.

l l SURVEILLANCE REQUIREMENTS 4.7.5.4 Each of the above required fire hose stations shown in Table 3.7.5.4-1 i

shall be demonstrated OPERABLE: .

i

a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

b. At least once per 18 months by:

i l 1. Visual inspection of the fire hose stations not accessible during l plant operation to assure all required equipment is at the station.

2. Removing the hose for inspection and reracking', and

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings,

c. At least once per 3 years by partially opening each hose station. valve to verify valve OPERABILITY and no flow blockage,

d. Within 5 years and between 5 and 8 years after purchase date and at least every 2 years thereafter by conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater.

l LA SALLE - UNIT 1 3/4 7-18 Amend..ent No. 23

PLANT SYSTEMS 3/4.7.6 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.6 All fire rated assemblies, including walls, floor / ceilings, cable tray enclosures and other fire barriers separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a f-irc orcc, e.r.d oli scclir.g device. iii Tiie rated a>>embly peneirailuns (iire " ~ ~ ~ ~

doors, fire windows, fire dampers, cable and piping penetration seals and ventilation seals) shall be OPERABLE.

• APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within one hour either establish a con- l tinuous fire watch on at least one side of the affected assembly (s) and/or device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and/or sealing device (s) and establish an hourly fire watch patrol. Restore the inoperable fire rated assembly (s) and/or sealing device (s) to OPERABLE status within 7 days or, prepare and submit a Special Report to the Commission l pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoperable fire rated assembly (s) and/or sealing device (s) and plans and schedule for restoring the fire rated assembly (s) and/or sealing devic'(s) e to OPERABLE status.

~ _

r

b. The provisions of Specification .0.3 and h are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.6.1 Each of the above required fire rated assemblies and sealing devices shall be verified to be OPERABLE at least once per 18 months by performing a visual inspection of:

a. The exposed surfaces of each fire rated assemblies.

b. Each fire window / fire damper ar)d associated hardware,

c. At least 10 percent of each type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10 percent of each type of sealed penetration shall be made. This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or abnormal degradation is found.

LA SALLE - UNIT 1 3/4 7-22 Amendment No. 23

PLANT SYSTEMS 3/4.7.10 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10 The main turbine bypass system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER..

ACTION:

With the main turbine bypass system inoperable:

1. If at least four bypass valves are capable of accepting steam flow per Surveillance 4.7.10.a:

a) Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

. 1) Restore the system to OPERABLE status, or i

2) Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Limit-ing Condition for Operation (LCO) to the main turbine '

bypass inoperable value per Specification 3.2.3.

M b) Otherwise, reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2. If less than four bypass valves are capable of accepting steam flow per Surveillance 4.7.10.a:

a) Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> increase the MCPR LCO to the main turbine by-pass inoperable value.per Specification 3.2.3, and b) Within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> restere the system to OPERABLE status, c) Otherwise, reduce THERMAL POWER to less than 25% of RATED l THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The provisions of Specification 3.0.4 are not applicabl SURVEILLANCE REQUIREMENTS 4.7.10 The main turbine bypass system shall be demonstrated OPERABLE at least once per:

a. 7 days by cycling each turbine bypass valve through at least one complete cycle of full travel. ,

LA SALLE - UNIT 1 3/4 7-33 Amendment No.58

o ELECTRICAL POWER SYSTEMS PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.2 All primary containment penetration conductor overcurrent protective devices shown in Table 3.8.3.2-1 shall be OPERABLE. .

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one or more of the primary containment penetration conductor mercurrent prctective devicts zhwn in T6ble 3.8.3.2-1 inupenule, restore the protective device (s) to OPERABLE status or de-energize

• the circuit (s) by tripping the associated circuit breaker or racking 4 out or removing the inoperable r.ircuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the circuit breaker to be tripped or the inoperable circuit breaker racked out, or removed, at least once per 7 days thereafter.

Othe mise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I

b. The provisions of Specification 3.0.4 are not applicable to over- Dk currentdevicesincircuitswhichhavetheircircuitbreakerstripped.j racked out, or removed.

SURVEILLARCE REQUIREMENTS 4.8.3.2 Each of the primary containment penetration conductor overturrent protective devices shown in Table 3.8.3.2- 1 shall be demonstrated OPERABLE:

l a. At least once per 18 months:

i

1. By verifying that the 6.9 kV and 4.16 kV circuit breakers l are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:

( a) A CHANNEL CALIBRATION of the associated protective relays, and An integrated system functional test of the breakers t

b)

! overcurrent protective trip circuit which includes simulated automatic actuation of the trip system to demonstrate that the overall penetration protection design remains within operable limits.

c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable i

type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

LASALLE-UNIT 1 3/4 8-22 Amendment No. 42 l

ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION i

3.8.3.3 The thermal overload protection of each valve shown in Table 3.8.4.2-1 shall be bypassed continuously or under accident conditions, as applicable, by an OPERABLE bypass device integral with the motor starter.

APPLICABILITY: Whenever the motor operated valve is required to be OPERABLE.

ACT_ ION:

With the thermal overload protection for one or more of the above required valves not bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device, take administrative action to '

D continuously bypass the thermal overload within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the ,

affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).

(b. The provisions of Specification 3.0.4 are not applicabl l SURVEILLANCE REQUIREMENTS i .

4.8.3.3.1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously or under accident conditions, as l applicable, by an OPERABLE integral bypass device by the performance of a i

CHANNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which are normally in force during plant operation and bypassed under accident conditions and by verifying that the thermal overload prntection is bypassed for those thermal overloads which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing:

a. At least once per 18 months, and i

b. Following maintenance on the motor starter.

4.8.3.3.2 The thermal overload protection for the above required valves which are continuously bypassed shall be verified to be bypassed following testing during which the thermal overload protection was temporarily placed in force.

l LA SALLE - UNIT 1 3/4 8-26 Amendment No.18 1

1

! . RADIDACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION ..

3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site

-(see Figure 5.1.1-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any or.gan, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6.A prepare and submit l to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid ef fluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commit-ment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include the radiological impact on finished drinking water supplies j at the nearest downstream drinkin water source,

b. The provisions of Specificatio 3.0.3 re not applicable.

L SURVEILLANCE REOUIREMENTS i

l 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODCM at least once per 31 days.

l l

l LA SALLE - UNIT 1 3/4 11-6 Amendment No. 23 i

1

. RADIDACTIVE EFFLUENTS L10VID WASTE TREATMENT SYSTEM F

LIMITING CONDITION FOR OPERATION T 3.11.1.3 The liouid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site (see Figure 5.1.1-1), when averaged over 31 days, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

APPLICABILITY: At all times.

ACTION: -

a. With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.A. prepare and submit to the l Commission within 30 days pursuant to Specification 6.6.C a Special Report which includes the following information:

1. ]dentification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of' action (s) taken to prevent a recurrence,

b. The provisions of Specificatio . 0. 3 nd 3.0.4 re not applicable.

SURVElllANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with tb ODCM.

4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste systect has been utiliied to process radioactive liquid effluents during the previous 92 days.

LA SALLE - UNIT 1 3/4 11-7 Amendment No. 23

RADIOACTIVE EFFLUENTS

/

LIQUID H0 LOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary tanks shall be limited to less than or equal to the limits calculated in the 00CM.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above list 2d tanks exceeding the above limit, immediately suspend all additions -

of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

A

b. The provisions of Specificatio s 3.0.3@3.0.4)arenotapplicable.

SURVEILLANCE REQUIREMENTS i

l 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

l l

W' LA SALLE - UNIT 1 3/4 11-8

RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 'Y 3.11.2.2 The air dose due to noble gases released in gaseous ef fl.aents, from each reactor unit, from the site (see Figure $.1.1-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to $ mr.ad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPL]CABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous ef fluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6. A, prepare and submit to the l Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

L

b. The provisions of Specificat'iof 3.0.3 h 3.0.4 re not applicable.

SURVEILLANCE REQUIREMENTS

~

~

4.11.2.2 Dose Calculations. Cumulative dose contributions for the current I

calendar quarter and current calendar year sh911 be determined in accordance with the ODCM at least once per 31 days. -

l l

l 1

l LA SALLE - UNIT 1 3/4 11-13 Amendment No. 23 1

RADIDACTIVE EFFLUENT $

DOSE - RAD 101001NES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM, AND

~-'

RAD 10NUCL1 DES o... OTHER THAN NOBLE GASES T

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiciodines and radioactive materials in particula.e form, and radionuclides, other than noble gases, with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited to the following: .

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radiciodines, radioactive materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding afly of the above limits, in lieu of any other report required by Specification 6.6. A. prepare and submit to the Commission within 30 days, pursuant to Specification 6.,6.C, a Special Report l which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Specificatio . 0. 3 I not applicable.

l SURVEILLANCE REQUIREMENTS I 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days. -

LA SALLE - UNIT 1 3/4 11-14 Amendment No. 23

RAD 10 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION '?

3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation. I APPLICABILITY: Whenever the main condenser air ejector system is in operation. I ACTION: .  !

i

a. With the GASEOUS RADWASTE TREATMENT SYSTEM inoperable for more than I 7 days, in lieu of any other report required by Specification 6.6.A, l prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.C a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and I the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE i status, and  :

3. Summary description of action (s) taken to prevent a recurrence.

9

b. The provisions of Specificatio 3.0.3(}nd3.0.4)arenotapplicable.

SURVE1LLANCE REQUIREMENTS l -

4.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days.

i ,

1 1

LA SALLE - UNIT 1 3/4 11-15 Amend ent No.23

r i

j' t

RADIDACTIVE EFFLUENTS  ;

VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION '?'

3.11.2.5 The appropriate portions of the VENTILATION EXHAU51 TREATMENT SYSTEM shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous ef fluent releases from each reactor unit, from the site (see figure 5.1.1-1), when averaged over 31 days, would exceed 0.3 mrem to any organ. .

APPLICABILITY: At all times.

ACTION:

a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than 31 days, or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit to the l Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence,

b. The provisions of Specificatioqp .0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the ODCH.

4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.

LA SALLE - UNIT 1 3/4 11-16 Amendment No. 23

I RADI0 ACTIVE EFFLUENTS i EXPLOSIVE GAS MIXTURE f

LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment ,

system shall be limited to less than or equal to 45 by volume.

i APPLICABILITY: Whenever the main condenser air ejector system is in operation.

ACTION:

a. With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,

b. The provisions of Specificatio 0.3 not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits as required by Table 3.3.7.11-1 of Specification 3.3.7.11, 1

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LA SALLE - UNIT 1 3/4 11-17 l

RADI0 ACTIVE EFFLUENTS VENTING OR PURGING.

LIMITING CONDITION FOR OPERATION 3.11.2.8 VENTING or PURGING of the containment drywell shall be through the Primary Containment Vent and Purge System or the Standby Gas Treatment System.

APPLICABILITY: Whenever the drywell is vented or purged.

ACTION:

a. With the requirements of the above specification not satisfied, suspend all VENTING and PURGING of the drywell.

b. TheprovisionsofSpecification(J70.3(d3.0.4 re not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.8.1 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Primary Containment Vent and Purge System or the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.

4.11.8.2 Prior to use of the Purge System through the Standby Gas Treatment System in OPERATIONAL CONDITION 1, 2 or 3 assure that:

a. Both Standby Gas Treatment System trains are OPERABLE, and

b. Only one of the Standby Gas Treatment System trains is used for i PURGING.

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LA-SALLE - UNIT 1 3/4 11-19 Amendment No.18 l

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RADIDACTIVE EFFLUENTS 3/4.11.3 SOLID RADIDACTIVE WASTE I LIMITING CONDITION FOR OPERATION _

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3.11.3 The solid radweste system shall be OPERABLE and used, as applicable in I accordance with a PROCESS CONTROL PROGRAM, for the 50L101FICAT10N and packaging l of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and )

of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times.

l ACTION: ,

1

a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR I Part 71 not satisifed, suspend shipments of defectively packaged '

solic radioactive wastes from the site. '

b. With the solid radweste system inoperable for more than 31 days, in i lieu of any other report required by Specification 6.6.A, prepare and l submit to the Commission within 30 days, pursuant to Specifi-cation 6.6.C. a Special Report which includes the following ,

information: 1

1. Identification of the inoperable equipment or subsystems and ,

the reason for inoperability, '

2. Action (s) taken to restore the inoperable equipment to OPERABLE status,

3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and

. 4. Summary description of action (s) taken to prevent a recurrence, n,

c. The provisions of Specificatio 3.0.3 are not applicable.-

SURVEILLANCE REQUIREMENTS 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at least once per 92 days by:

a. Operating the solid radwaste system at least once in the previous 92 days in accordance with the Process Control Program, or

b. Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

LA SALLE - UNIT 1 3/4 11-20 Atendment No. 23

RADIDACTIVE EFFLUENTS 3/4.11.4 TOTAL 005E LIMITING CONDITION FOR OPERATION .

3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. .

APPLICABILITY: At all times.

ACTION: ,

a. With the calculated' doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica- '

tions 3.11.1.2.a. 3.11.1.2.b 3.11.2.2.a. 3.11.2.2.b. 3.11.2.3.a. or 3.11.2.3.b, in lieu of any other report required by Specification 6.6.A, l prepare and submit, pursuant to Specification 6.6.C, a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4.

This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release (s) cen red by this report. If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of K 190.11. Submittal of the report is considered a timely request, l

and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification.

b. The provisions of Specificatio 0.3 and 3.0.4 re not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordt.nce with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the ODCM.

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LA SALLE - UNIT 1 3/4 11-22 Amendment No. 23

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

[ ~ 3/4.12.1 MONITORING PROGRAM 3

LIttlTING CONDITION FOR OPERATION _

3.12.1 The radiological environmental monit$ ring program shall be conducted as specified in Table 3.12.1-1.

APF LICABILITY: At all times.

ACTION: .

a. With the radiological environmental monitoring program not being conducted as-specified in Table 3.12.1-1, in lieu of any other report required by Specification 6.6.A. prepare and submit to the l Cc+ mission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program es required and the plans for preventing a recurrence.

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels in Table 3.12.1-2 when averaged over any calendar quarter, in lieu of any other report required by Specifi-catica 6.6. A, prepare and submit to the Commission within 30 days i from the end of the affected calendar quarter a Special Report I pursuant to Specification 6.9.1.13. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

cencentration (1) concentration (2) + ***> 1.0 limit level (1) 1,imit level (2) -

When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater

- than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With milk or fresh leafy vegetable sampics unavailable from one or more of the sample locations required by Table 3.12.1-1, in lieu of any other report required by Specification 6.6.A, prepare and submit l to the Commission within 30 days, pursuant to Specification 6.6.C, a i Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples.

The locations from which samples were unavailable may then be deleted from those required by Table 3.12.1-1, provided the locations from which the replacement samples were obtained are added to the environ-mental monitoring prcgram as replacement locations.

d. The provisions of Specificatio .0.3 and 3.0.4 re not applicable.

LA SALLE - UNIT 1 3/4 12-1 Amendment No.23

d RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS 2

LIMITING CONDITION FOR OPERATION

. 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal and the nt arest residence in each of the 16 meteor- l

. ological sectors within a distance '.,f five miles. (For elevated releases as l defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall al;;o identify the locations of all milk animals in each of the 16 meteoro- i logical sectors within a distance of three miles.) )

APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) which yields a i calculated dose or dose commitment greater than the values currently I being calculated in Specification 4.11.2.3, in lieu of any other l report required by Specification 6.6.A., prepare and submit to the l Commission within 30 days, pursuant to Specification 6.6.C., a i Special Report which identifies the new location (s).

b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.6.A., prepare and l l submit to the Commission wi tion 6.6.C., a Special Repo, thin 30 rt which days, pursuant identifies the new location. to Specifica-The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding ,

the control station location, having the lowest calculated dose or  !

dose commitment (via the same exposure pathway) may be deleted from ,

this monitoring program after (October 31) of the year in which this .

land use census was conducted.

c. The provisions of Specificatiorfa)3.0.3 re not applicable.  !

SURVEILLANCE REOUIREMENTS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of (June 1 and October 1) using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

LA SAI.LE - UNIT 1 3/4 12-9 Amendment No. 23

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-RADIOLOGICAL ENVIRONMENTAL MONITORING

-3/4.12.3 INTERLABORATORY COMPARISON PROGRAM  %='

s-LIMITING CONDITION FOR OPERATION i

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l-3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the "

Commission.

APPLICABILITY: At all times.

ACTION:

r.

L a. With analyses not being performed as required above, report the i corrective actions taken to prevent a recurrence to the Commission I in the Anr.ual Radiological Environmental Operating Report, b, TheprovisionsofSpecification()IO3 nd 3.0.4 re not applicable.

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SURVEILLANCE REQUIREMENTS l

4.12.3 A summary of the results obtained as part of the above required Inter- '-

laboratory Comparison Program and in accordance with the ODCM (or participants l in th EFA crosscheck program shall provide the EPA program code designation I

for the unit) shall be included in the Annual Radiological Environmental

. Operating Report.

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1 LA SALLE UNIT 1 3/4 12-10

Aeo ras.w PA c-a.s e

i K4. 0 APPLICABILITY BAS The ecifications of this section provide the general requirements applicable o each of the Limiting Conditions for Operation and Surveil ince

-Requirements ithin Section 3/4. In the event of a disagreement betw n the 1 requirements ated in these Technical Specifications and those stat in an applicable Regu tion or Act, the requirements stated in the appli ble Regulation or Ac shall take precedence and shall be met.

3.0.1 This sp cification states the applicability of en specification in terms of defined ERATIONAL CONDITION or other specified pplicability condition and is prov d to delineate specifically when e h specification is applicable.

3.0.1 This specifi ion defines those condition necessary to constitute compliance with the terms o( an individual Limiting ndition for Operation and associated ACTION requirement.

3.0.3 _This specificatiod elineates the me sures to be taken for circumstances not directly provided for in t ACTION stateme s and whose occurrence would violate the intent of the specification. For example, pecification 3.7.2 requires two control room and auxiliary electric equipment room 6 rgency filtration trains to be OPERABLE t

and provides explicit ACTION requirements i one train is inoperable. Under the requirements of Specification 3.0.3,\$f b th of the required trains are inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> measures must be initiate o place the unit in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least sSHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the subseque 24shours. As a further example, Specifi-cation 3.6.6.1 requires two primary ontainpent hydrogen recombiner systems to be OPERABLE and provides explicit ACT N requirements if one recombiner system is inoperable. Under the requireme s of Specification 3.0.3, if both of the required systems are inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />' measures must be initiated to place the unit in at least STARTUP thin the next 6 h'ours and in at least HOT SHUTDOWN within the following 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> It is acceptable to initiate s and complete a reduc-tion in OPERATIONAL CONDIT S in a shorter time interval than required in the ACTION statement and to a the unused portion of this allowable out-of-service time to that provided f operation in subsequent lowe'r 0PERATIONAL s CONDITION (S).

Stated allowable out- service times are applicable reggrdless of the OPERATIONAL CONDITION (S) in whic the inoperability is discovered but\the times provided for achieving a CONDIT N reduction are not applicable if the inoperability is discovered in a C DITIONlowerthantheapplicableCONDITIOQ.

3.0.4 Th specification provides that entry into an OPE ATIONAL CONDITION must be made th (a) the full complement of required systems, uipment or components RABLE and (b) all other parameters as specified i he Limiting Conditions or Operation being met without regard for allowable di iations and out of se vice provisions contained in the ACTION statements. .

T intent of this provision is to ensure that unit operation issnot initi ed with either required equipment or systems inoperable or othe limits bei exceeded. .

Exceptions to this provision have been provided for a limited number of ecifications when startup with inoperable equipment would not affect pikt safety. These exceptions are stated in the ACTION statements of the approp iate specifications.

LA SALLE - UNIT 1 B 3/4 0-1 Amendment No. 1

. . . _ _ _ _ _ _ _ _ _ _ _ _ = _

b AP9LICABILIfY BA3ES o

v 3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION state-ments for power sources, when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components or devices to be consistent with the ACTION statements of the associated electrical power source. It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be fnoperable solely because of the inoperability of its normal or emergency power source. The pro-visions of Specification 3.0.5 are not applicable to the HPCS system, electrical division 3 or diesel generator 1B.

For example, Specification 3.8.1.1 requires in part that emergency diesel generators 0 and 1A be OPERABLE. The ACTION statement provides for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> out-of-service time when emergency diesel generator 0 or 1A is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systes:s, subsystems, trains, components and devices supplied by the inoperable emergency power source, diesel generator 0 or 1A, U would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable Limiting Conditions for Operation.

However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emer0ency diesel generator instead, provided the other specified conditions.are satisfied. In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE,'or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE). If they are not satisfied, action is required in accordance with this specification.

As a further example, Specifiestion 3.8.1.1 requires in part that two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE. The ACTION statement provides a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> out-of-service time when both required offsite circuits are not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specifica-tion 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable. This would dictate invoking the applicable ACTION state-ments for each of the applicable LC01 However, the provisions of Specifica-tion 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied. In this case, this would mean that for one division the emergency power source must be OPERABLE LA SALLE - UNIT 1 B 3/4 O M

,4 APPLICABILITY

- BASES 3.0.5 (Continued)

(as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e. , be capable of performing their design functions and have an emergency power source OPERABLE). In other words, both emergency power sources 0 and 1A must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE. If these conditions are not satisfied, action is required in accordance with this specification.

In OPERATIONAL CONDITION 4 or 5, Specification 3.0.5 is not applicable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation in these OPERATIONAL CONDITIONS must be adhered to.

4.0.1 This specification provides that surveillance activities neces .y to ensure the Limiting Conditions for Operation are met and will be perfo ed dur the OPERATIONAL CONDITIONS or other conditions for which the Lim ing Condi 'ons for Operation are applicable. Provisions for additional sp veillance activit. s to be performed without regard to the applicable OPERATIONAL CONDI-TIONS or o er conditions are provided in the individual Surveillpn'ce Require-ments. Surv llance Requirements for Special Test Exceptions n d only be performed when .he Special Test Exception is being utilized a an exception to an individual sp ification.

4.0.2 The provisi as of this specification prov' e allowable tolerances for performing surveillances activities beyond thos . pecified in the nominal surveillance interval. These tolerances are nec sary to provide operational flexibilit "at least"y associated because ofwith scheduling and performa e considerations. The phrase a surveillance fr uency does not negate this allowable tolerance; instead, it pi mits e more frequent performance of surveillance activities.

The allowable tolerance for perform ng s veillance activities is sufficiently restrictive to ensure that the reJ4} ability ssociated with the surveillance degraded beyon that obtained from the nominal activityisnotsignificantly/otintendedtha surveillance interval. It is the allowable tolerance be used as a convenience to repeatedly schedule the erformance of surveillances at the allowable toleran limit.

4.0.3 The provi ons of this specification set th the criteria for determination of c liance with the OPERABILITY require ts of the Limiting Conditions for 0 ration. Under this criteria, equipment, stems or components are assumed to e OPERABLE if the associated surveillance act ities have been satisf actori) performed within the specified time interval. N ing in this provision 's to be construed as defining equipment, systems or com nents OPERABL , when such items are found or known to be inoperable althou still meeti the Surveillance Requirements.

SALLE - UNIT 1 B 3/4 0-3 AMENDMENT NO. 68 1

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

APPLICABILITY BASES .

4.0.4 This specification ensures that surveillance activi es associated ith a Limiting Conditions for Operation have been performed w hin the s cified time interval prior to entry into an applicable OP ATIONAL CO ITION or other specified applicability condition. The tent of this prov'sion is to ensure that surveillance activities have en satisfactorily demon trated on a current basis as required to meet the ERABILITY requir ents of the Limiting Condition for Operation.

Unde the terms of this specification, for examp e, during initial plant startup or following extended plant outage, the appl cable surveillance activities st be performed within the stated sur 111ance interval prior to placing or te urning the system or equipment into PERABLE status.

4.0.5 This pecification ensures that i ervice inspection of ASME Code Class 1, 2 and 3 mponents and inservice t ting of ASME Code Class 1, 2 and 3 pumps and valves ill be performed in ac rdance with a periodically updated version of Section X of the ASME Boiler nd Pressure Vessel Code and Addenda as required by 10 CFR 0, Section 50.55 . Relief from any of the above requirements has been p vided in writ g by the Commission and is not a part of these Technical Speci cations.

This specification inci des a larification of the frequencies of performing the inservice insp ti and testing activities required by u Section XI of the ASME Boiler a Pressure Vessel Code and applicable Addenda, i

This clarification throughout is provided these Technical Sp ifbensureconsistencyinsurveillanceintervals ations and to remove any ambiguities relative to the frequencies' r part rming the required inservice inspection and testing activities.

Under the terms of is specificat gn, the more restrictive requirements L of the Technical Specif cations take preckdence over the ASME Boiler and

,. Pressure Vessel Code d applicable Addendh For example, the requirements of L Specification 4.0.4 o perform surveillance \ etivities prior to entry into an OPERATIONAL CONDIT N or other specified app ability condition takes precedence over t ASME Boiler and Pressure ,sel Code provision which allows pumps to e tested up to one week after rgturn to normal operation.

And for exampi , the Technical Specification deff tion of.0PERABLE does not l grant a grace period before a device that is not c able of performing its l specified f ction is declared inoperable and takes recedence over the ASME Boiler an . ressure Vessel provision which allows a lve to be incapable of

, performi its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b fore being declared l inopera e.

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l LA SALLE - UNIT 1 B 3/4 0-4

3/4'.0 APPLICABILITY l ____________________

! BASES e====================================================u===================r===

Specifications 3. 0.1 throuch 3. 0. 4 establish the general requirement s applicable to the Limiting Conditions for Operation. These requirement s are

- based on the requirements for the Limiting Conditions for Operation, as stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2):

" Limiting Conditions for Operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a Limiting Condition for Operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the

' condition can be met."

Snecification 3.0.1 establishes the Applicability statement, located within each individual specification, as the requirement for when (i.e. , in which OPERATIONAL CONDITIONS or other specified CONDITIONS) conformance to the Limiting Conditions for Operation, is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits, when the requirements of a Limiting Condition for Operation is not met. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (rout ine) voluntary. removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic types of ACTION requirements. The first specifies the ,

remedial measures that permit continued operation of the f acility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Conditions for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in an OPERATIONAL CONDITION or other specified CONDITION in which the specification no longer applies.

The specified time limits of the ACTION requirements are applicable f r om the point in time it is identified that a LimitinD Condition for Operation is not met. The time limits of the ACTION requirements are also applicable when a system or ccmponent is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified t ime limit for the complet ion of a Surveillance Requirement when equipment is removed from service. In this case, the allowable outage time limits of the ACTION requirements are appliccJle when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable, in this case, the time limits of the ACTION requirements would apply from the point in time that LASALLE - UNIT 1 B 3/4 0-1 DROPOSED AMENDMENT

3/4.0~ APPLICABILfTY

+

DASES~.

=================================================================

'the new= specification becomes applicable if the requirements of the Limiting

. Condition for Operation are .not met.

Oneeffication 3.0.2. establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specificatien is to clarify

-that (1) . implementation of the ACTION requirements within the specified stime interval constitutes compliance with a specification and (2) completion of the remedial measures of. the ACTION requirements is not required when compliance-

~w ith a. LimitinD Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3. 0. 3. establishes the shutdown ACTION requirements that must

,~

be' implemented when a" Limiting. Condition for Operation is not met and the condit ion -is -not specifically addressed by the associated ACTION requirement s.

-The purpose of this specification is to delineate the time limits for placing the. unit in a safe shutdown CONDITION when plant operation cannot be maintained within the limits for safe operation -defined by the_ Limiting Conditions for Operation and its ACTION requiroments. It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components ;being inoperable. One hour is allowed to prepare for'an orderly shutdown before

initiating a change in plant operation. _This time. permits the operator to

coordinate the' reduction in electrical. generation with the' load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach. lower CONDITIONS of- operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces. thermal tstresses on . components of' the primary coolant system and the potential for a i plant. upset that could challenge safety systems under CONDITIONS for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown mayLbe terminated. The time limits of the ACTION requirements are applicable from 'the point in the time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION

-requirements have been met or the time limits of the ACTION requirements have j(, not expired, thus providing an allowance for the completion of the required actions.

The time limits of Specification 3.0.3. allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in COLD- SHUTDOWN when a shutdown is required during p0WER operation. If the f[

i plant is in a lower CONDITION of operation when a shutdown is required, time limit for reaching the next lower CONDITION of operation applies.

the However, if a lower CONDITION of operation is reached in less time than I allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL 3 LASALLE - UNIT 1 B 3/4 0-E PROPOSED AMENDMENT V

F, 61;

3/4.0 APPLICABILITY DASES

====nn===========================================================

CONDITION, is.not reduced. For example, if STARTUP is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measurer are completed that would permit a return to POWER operation, a penalty is not' incurred by having to reach a lower CONDITION of operation in less then the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION. requirements for one specification results in entry into an OPERATIONAL CONDITION or CONDITION of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outaDe time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the hilowable outage time that is applicable when a Limiting Condition for Operation'is not met in a lower CONDITION of operation.

The shutdown _ requirements of specification 3.0.3. do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial measures to be iaken.

Specification ?.0.4 establishes limitations- on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result'in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that hi Dher CONDITIONS of operation are not entered when correcti've action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation l without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified CONDITION may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of specification 3.0.4. do not apply because they would delay placing the facility in a lower CONDITION of operation.

LASALLE - UNIT 1 B 3/4 0-3 PROD 03ED AMENDMENT

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Specification 3.0.5 2

(The bases for Specificction 3.0.5 remain unchanged.)

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Snecifications 4. 0, l' . throuah 4. 0. 5. establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance RequirementLstated in the Code of Federal Regulations, 10 CFR

50. 36 (c) (3) :

" Surveillance requirements are requirements relating to test, calibratlon,- or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the Limiting Conditions of Operation will be met."

' Specification 4. 0.1 establishes the requir went that surveillances must be performed durinD the OPERATIONAL CONDITIONS or-other CONDITIONS for which the requirements' of the Limiting Conditions for Operation apply unless otherwise t

stated in an itidividual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the

[ , operational status of systems and components and that parameters are within r specified ~ limits to ensure safe operation of the facility when the plant is in an OPERATIONAL-CONDITION or other specified condition for which the individual f

' Limiting ~ Conditions for Operation are applicable.- Surveillance Requirements do not have to be performed when the. facility is in-an OPERATIONAL. CONDITION i' for _w hich the requirements of the associated Limited Condition for Operation f do not ' apply unless otherwise specified. The Surveillance Requirements b associated with a Special Test Exception are only applicable when the Special g Test Exception is used as an allowable exception to the requirements of at specification.

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! Specification 4.0.2. establishes the conditions under which the specified n

p time interval for Surveillance Requirement s may be extended. The specification permits an allowable extension of the normal surveillance

[ interval; to. facilitate surveillance scheduling, and consideration of plant R operatinD CONDITIONS, that may not be suitable for conducting the

~h surveillance; e.g., transient conditions or other ongoing surveillance or

-maintenance activities. The limit given in Specification 4.0.2 is based on engineering ,)udgement and the recognition that the most probable result of any '

particular surveillance being performed is the verification of conformance

.with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured throuDh surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. It is not intended that the allowable tolerance be used as a

. convenience to repeatedly schedule the performance of surveillances at the allowable tolerance limit.

Spec t rica t ion 4. 0. 3. establishes the failure to per form a Surveillance Requirement within the allowed surveillance interval, defined by the.

provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

. Under the provisions of this speci ficat ion, systems and comoonents are assumed to be OPERABLE when Surveillance Requirements have been sat isf act ori ly performed within the specifie1 time interval. However, nothing in this h LASALLE - UNIT 1 B 3/4 0-5 PROPOSED AMENDMENT w .

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Q[ * [ * ( OPERABLE whenf they are?found(or: known; to- be inoperable althoughnst'illi meeting?

Mgthe Surveill'ance1 Requirements. Thisl specification Ralso : clarifies: that thei>

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q M ACTION Yrequirements 1 areVapp11 cable ~ _ when' Surveillance Requirement s have' not ;

$C (p V j beenicompletedLwithin thefallowed surveillance; interval cand that? the.; time :p

• '-- A ~I31mitsU, oft thel ACTION requirements ' apply ifrom ithe point fin s time itLis R%$ , pu lidentified that; a surveillance has not _ been performed and not at theltime that NK $$ . Othe yallcwedi j surve111ancel f interva1{ was:: exceeded.) f Completion? of eithe= .

. - ;SurveillanceiRequirement' within the allowable outage time limitscof .the- ACTION:

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4 /requirementsPrestoresl compliance with}thi requirements of_ , Specification 4 0.3. -

Qq A fHowever,1(thisidoes not; negate) the fact that the failure to have performed; Lthen -

N^ ,,isurve111snee 'within? t. hey allowed surveillance ' interval,- defined ;tiyx the

%6- 7 provisions ;of SSpecificationf 4.0.2, - l wasi a : violat ton. of - thef OPERABILITYL hpg ' & _ requirements (;of: zaDiLimiting: Condition for Operation . that g is: sub,)ect Lto~

Sgm  ; enforcement? action M Further,-the-failure to perform;a surveillance within the: , @Q s provisions; of? Specification 4.0.2)isla violation.of'a Technical Specification: d

@gg'f~ q', " requirement fandiisiitherefore, afreportablefevent under the. requirements ofJ10; 4 f i + l CFR p 50. 73(a) (2hi)'.(B)-- - because fit is .a condition'proh'ibited bycthe;; plan,tjs e [

1. ;e '

iTechnicalT Specifications. - '

Mp gg a 5: <g 11fM theVallowable_ outagestime . limits of the; ACTION requirements arelless 7than, .J

,y , ,

124; hours:or7a shutdownnisfrequired to comply with ACTION _. requirements,,_e.g.,- MlM (Speci ficat ion 73. 0. 3. ,; a1 24-hour 7 allowance is provided to: permit' a'delaysin-

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fcomplete?!S_urveillance Requirements;that.have:not been performed. The purpose Coffthlisfallowance(isito; permit;the1 completion; ofa:a ' surveillance before .a;

> ] 3y i' y . ;shutdownh would'betrequiredito' comply'with ACTION _ requirements or before other-: -

1 1, s ;remedialfmeasures would-be required that-may prec1_ude ;the _completionLof "a-  ;

surve'111ance. - iThec' basis for this allowance _ includes considerat~ ion for

plant- 4 f(

j7P w qconditions,Jadequate planning,. availability of personnel, the' time required:to

%jJ fperfor_msthej surveillance,1- .and the' safety significance of ;theLEdelay in1 ..

• f completing theLrequired surveillance. ,This : provision'. Lalsk provides: i' time y, .

3 Elimit = forf'fthe completion of Surveillance Requirennts thatL become applicabler

{ug fn ,

Jas7 La' cohsequenceVof f 0pERATIONALu : CONDIT10N' chenges ' imposed ~ ,by -

' ACTION: }

>>> ~ z requirements and. for completingiSurveillance" Requirements that: are applicable - A a9M , $ heni an exception'to the requirements of_ Specification 4.0.4 isfallowed. If a j c Tsurvell' lance is not completed within the 24-hour. allowance, the'timerlimits_off 4,  ;{

, , , 1tha ACTION: requirements are applicable at that time.; When a' surveillance is' i d, . .

i performed (within .the'24-hour allowance and the Surveillance Requirements are j j '

(notfmet, the; time limits of the ACTION requirements are applicable at the time: -j 9F J ithat the surveillance is terminated.. O 3

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---. . t NF L  ; Surveillance requirements do not have to be performed on inoperable equipment  ;

Y m 1because the ACTION frequirements define the remedia1 measures that apply. 4 S ,

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DHowever, the Surveillance Requirements.have to be met to demonstrate that '

h iinoperable equipment has been restored to OPERABLE status.

5 - Specification 4. 0, 4. establishes the requirement that all applicable 3 fik '

surveillances must be met before entry into an OPERATIONAL CONDITION or other .

< condition of. operation specified in the Applicability statement. The purpose- e a i )

/LASALLE - UNIT 1- B 3/4 0-6 PROPOSED AMENDMENT

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of this specification is to ensure thac system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified CONDITIONS associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance requirements must be performed within the specified surveillance interval to ensure that the LimitinD Conditions for Operation are met during initial plant  ;

startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions i of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

Speci ficat ion 4. 0. Q.._

. establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code  !

Class 1, 2,'and 3 pumps and valves shall be performed in accordance with a }

periodically- updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements {

x apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing the inservice inspection and testinD activities required by Section XI of the l ASME Boiler and pressure Vessel Code and applicable Addenda. This  ;

l clarification is provided to ensure consistency in surveillance intervals l throughout.the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure l

j Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 )

to perform surveillance activities before entry into an OPERATIONAL CONDITION

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or other specified condition takes precedence over the ASME Boiler and l Pressure Vessel Code provisions that allows pumps and valves to be tested up )

to one week after return to normal operation. The Technical specification

. definition of OPERABLE does not allow a grace period before a component, which ,

is not capable of performing its specified function, is declared inoperable l and takes precedence over the ASME Boiler and Pressure vessel code provision i that allows e valve to be incapable of performing its specified function for  !

up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

i l

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! LASALLE - UNIT 1 B 3/4 0-7 PROPOSED AMENDMENT j

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3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the sucededing Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

! 3.0.3 When a Limiting Condition for Operation is not met, except as provided l in the associated ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

1. At.least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

! 2. At least HOT SHUT 00WN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTOOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

e Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual l Specifications.

This specification is not applicable in OPERATIONAL CONDITION 4 or 5.

V c6 P11N 3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall QM not be made unless the conditions for the Limiting Condition for Operation are l I g6d met without reliance on provisions contained in-the ACTION requirements. This provision shall not prevent passage through OPERATIONAL CONDITIONS as required t

'4 to comply with ACTION requirements. Exceptions to these requirements are stated in the individual-Specifications.

3.0.5 When a system, subsystem, train, component or device is determined to

( '

be inoperable solely because its emergency power source is inoperable, or I

solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s),

subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise

! satisfy the requirements of this specification. Unless both conditions (1) l and (2) are satisfied, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action shall be initiated to place the unit in an OPERATIONAL CONDITION in whf 'h the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in:

1. At least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and l 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This specification is not applicable in OPERATIONAL CONDITION 4 or 5.

LA SALLE - UNIT 2 3/4 0-1

f. , ._

APPLICABILITY I f[ og f.Ac6 B

Wll'H]

usB SURVEILLANCE REQUIREMENTS i

4.0.1 Surveillance Requirements shall be et during the OPERATIONAL CONDITIONS or other conditions specified for individifal Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirements.

4.0.2 Each Surveillance Requirement shal be performed within the specified surveillance interval with a maximum allo vable extension not to exceed 25 percent of the specified surveillance interval.

Failure to perform a Surveillance Requirement within the specified tim

[4.0.3 interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications. Surveillance requirements do not have to be performed on inoperable equipment.

4.0.4 EntryintoanOPERATIONALCONDITIONo[otherspecifiedconditionshall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves ,

shall be performed in accordance with Sect, ion XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by ,

l LWg .10 CFR 50, Section 50.55a(g), except where specific written relief

'T has been granted by the Commission pursuant to 10 CFR 50, Section 4gJM7 50.55a(g) (6) (i).

C, b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days

• Not applicable to 18 month surveillances required for Unit 2 Cycle 2 operation.

LA SALLE - UNIT 2 3/4 0-2 AMENDMENT NO. 50

LNSERT A 3.0.4 Entry into an OPERATIONAL CONDITION or other specified CONDITION shall not be made when the conditions for the Limiting Conditions for i Operations are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL CONDITION may be made in accordance with the ACTION requirements when conformance to them permits continued operation of

.the facility for an unlimited period of time. This provision shall not prevent passage though or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications. '

! INSERT B 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a L Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time litaits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.

INSERT C 11 i

l 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable CONDITION shall not be made unless the Surveillance Requirements associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to l

OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

l l 0444T:8 L

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1 REACTIVITY CONTROL SYSTEM.

LIMITING CONDITION FOR OPERATION (Continued) i l

ACTION (Continued)

2. If the inoperable control rod (s) is inserted:

a) Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> diserin the associated directional control l valves" either 1). Electrically, or l

l 2) Hydraulically by closing the drive water and exhaust water isolation valves, b) Otherwise, be in at least HOT SHUTDOWN within the next-12 hours. '

The provisions of Specification 3.0.4 are.not applicabl c.- With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS l l'

I- 4~.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

a. At least once per 31 days verifying each valve to be open**, and

b. At least once per'92 days cycling each valve through at least one complete cycle of full travel.

1 4.1.3.1.2 When above the low power setpoint of the RWM and RSCS, all withdrawn control rods not required to have their directional c'ontrol valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each 1

control rod at least one notch:

a. At least once per 7 days, and

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immovable as a result of excessive friction or mechanical interference.

4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4.1.3.2, 4.1.3.4, 4.1.3.5, 4.1.3.6, and 4.1.3.7.

l "May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

• • These valves may be closed inter.mittently for testing under administrative control.

l LA SALLE - UNIT 2 . 3/4 1-4 l

L

7 1

, c REACTIVITY CONTROL SYSTEM.

t CONTROL ROD MAXIMUM SCRAR INSERTION TIMES e

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 and 2.

l ACTION:

ia With th maximum scram insertion time of one or more control rods p exceeding 7 seconds:

1.

Declare the control rod (s) with the slow insertion time inoperable, and 1 i

I,

2. Perform the Surveillance Requirements of Specification 4.1.3.2c.

i p at least once per 60 days wh or more control rods with ma.en operation is continued with three i

ximum scram insertion times in excess of 7 seconds.

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

[b. The provisions of Specification 3.0.4 are not applicable 1

i 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  !

equcl to 950 psi

-rod drive pumpsisolated g and, from duringthesingle control rod scram time tests, the control accumulators:

i

a. For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS

• or after a reactor shutdown that is greater than 120 days, l b. For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those l specific control rods, and 1

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 l rod movement.

i i

LA SALLE - UNIT 2 3/4 1-6 Amendment No. 53

F g

REACTIVITY CONTROL-SYSTEM FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES 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:

a 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 2. l ACTION:

cay'Withtheaveragescraminsertiontimesofcontrolrodsexceed the above limits:

4--

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.

1. at least once per 60 days when operation is continued with an I

average scram insertion time (s) in excess of the average scram insertion time limit.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(b. TheprovisionsofSpecification3.0.4arenotapplicable.)

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.

i LA SALLE - UNIT 2 3/4 1-8 Amendment No.

53

~

F 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 1, 2, and 5*

l ACTION: ,

a. In OPERATIONAL CONDITION 1 or 2:

1. -With one control rod scram accumulator inoperable:

a) Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, either: .

1) Restore the inoperable accumulator to OPERABLE status, or

2) Declare the control rod associated with the inoperable accumulator inoperable, b) Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation 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.

h The provisions of Specification 3.0.4 are not applicable "At least the accumulator associated with each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

I LA SALLE - UNIT 2 3/4 1-9 Amendment No. 53

c; REACTIVITY CONTROL SYSTEM

-CONTROL ROD DRIVE COUPLING

LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: -OPERATI6NAL CONDITIONS 1, 2, and 5*.

l ACTION:

a. In OPERATIONAL CONDITIONS 1 and 2 with one control rod not coupled to.

its associated drive mech:nt:m: -

1. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either: -

a) If permitted by.the RWM and RSCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

1) Observing any indicated response of the nuclear instrumentation, and

2) Demonstrating that the control rod will not go to the overtravel position.

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

2) Hydraulically by closing the drive water and exhaust water isolation valves.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

i 1. Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating 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.

The provisions of Specification 3.0.4 are not applicable.)

h.

• At least each wit.hdrawn 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 associated with restoring the control rod to OPERABLE status, d

LA SALLE - UNIT 2 3/4 1-11 Amendment No. 53

REACTIVITY CONTROL SYSTEM-LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod position indicator inoperable, move the control rod to a position with an OPERABLE position indicator or insert the control rod.

{. The provisions of Specification 3.0.4(are not applicabl I c SURVEILLANCE REQUIREMENTS l

4.1.3.7 The control rod position indication system shall be determined OPERABLE L by verifying:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the position of each control rod is I indicated,

b. That the indicated control rod position changes during the movement of the control rod drive when performing Surveillance Requirement-4.1.3.1.2, and

c. That the control rod position indicator corresponds to the control rod position indicated by the " Full out" position indicator when performing Surveillance Requirement 4.1.3.6b. '

l

d. That the control rod position indicator corresponds to the control rod position indicated by the " Full in" position indicator:

1. Prior.to each reactor startup, and

2. Each_ time a control rod is fully inserted.

l l

"At least each withdrawn control rod not applicable to control rods removed per Specifications 3.9.10.1 or 3.9.10.2.

LA SALLE - UNIT 2 3/4 1-14 Amendment No. 14

I REACTIVITY CONTROL SYSTEM 3/4.1.4 CONTROL ROD PROGRAM CONTROLS ROD WORTH MINIMIZER LIMITING CONDITION FOR OPERATION ,

3.1.4.1- The rod worth minimizer (RWM) shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*, when THERMAL POWER is less l than or equal to 20% of RATED THERMAL POWER, the minimum allowable low power setpoint.

ACTION:

With the RWM inoperable, verify control rod movement and compliance with the prescribed control rod pattern by a second licensed operator e 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 applicabl 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 reaching 20% of RATED THERMAL POWER when reducing THERMAL POWER, by verifying proper 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 block function by demonstrating inability to withdraw an out-of-sequence control rod,

c. In OPERATIONAL CONDITION 1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after RWM automatic initiation when reducing THERMAL POWER, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence 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 withorawal 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, i

LA SALLE - UNIT 2 3/4 1-16 Amendment No. 53

l l

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEN INSTRUMENTATION LINITING CON 0! TION F03 QPERATION l

! 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERA 8LE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

l ACTION:

L l a. With the number of OPERA 8LE channels less than required by the Mini-

! aus 0PERA8LE Channels per Trip System requirement for one trip system, place the inoperable channels and/or trio systos in the trioned con- l dit' on* within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.(The provisions of Spec' fication 3.0.4 are not

~ ,

app'icable M

b. With the the number of OPERA 8LE channels less than required by the Minimum OPERA 8LE Channels per Trip System requirement for both trip l systems, place at least one trip system ** in the tripped condition L within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS

! 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL l

CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

- 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trio I functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one chaenel per trip system such that all channels are tested at least once every Ntimes18monthswhereNisthetotalnumberjofredundantchannelsina specific reactor trip system.

"With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERA 8LE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.  :

• • If more channels are inoperable in one trip system than in the other, select that trip system to place in the tripped condition, except when this would cause the Trip Function to occur.

LA SALLE - UNIT 2 3/4 3-1 Amendment No.17

[ 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION -

L LIMITING CONDITION FOR OPERATION L

3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be ODERABLE with their trip setpoints set consistent with the values shown in me Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONhE LIME as shown in Table 3.3.2-3.

l APPLICABILITY: As shown in Table 3.5.2-1.

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, i

b. With the-number of OPERABLE channels less than required by the l Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or trio system in the l

trioned condition

• within one hour. Qhe provisions of Specifica-tion 3.0.4 are not applicablDLn

c. With the number of OPERABLE channels less than required by the

-Minimum OPERABLE Channels per Trip System requirement for both trip l, systems, place at least one trip system ** in the tripped condition *** l within one hour and take the ACTION required by Table 3.3.2-1. l I

• An inoperable channel need not be placed in the tripped condition where this l would cause the Trip Function to occur. In these cases, the inoperable l l

channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION f required by Table 3.3.2-1 for that Trip Function shall be taken.

• • If more channels are inoperable in one trip system than in the other, select that trip system to place in the tripped condition except when this would cause the Trip Function to occur.

• • • An inoperable channel need not be placed in the tripped condition where this

~

would cause'the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or the ACTION l required by Table 3.3.2-1 for that Trip Function shall be taken, l

i.

l l

LA SALLE - UNIT 2 3/4 3-9 Amendment No.14 1

l l l .__- - __-____-__- _ _ - ----- - _ _ - _ _ _ - _ _ - _ _ - - _ _ - _ _ _ _ _ _ _ _ _ _ _ _

i TABLE 3.3.3-1 (Continued)

EMERGENCY CORE C0OLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a. With one channel inoperable, place the rable channel in the tripped condition within one ho

• or declare the associated system inoperable,

b. With more than one channel inoperable, declare the associated system inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip Function, place the inoperable  ;

channel in the tripped condition within one hour; restore the l inoperable channel to OPERABLE status within 7 days or declare the associatsd system inoperable, i

ACTION 32 - With the number of OPERABLE channels less than required by l

the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ADS trip system or ECCS inoperable.

ACTION 33 - With the number of OPERABLE chan'nels less than the Minimum ,

OPERABLE Channels per Trip Function requirement, place the I inoperable channel in the tripped condition within one hour.

ACTION 34 - With the number of OPERABLE channels less than required by the -l Minimum OPERABLE Channels per Trip Function requiremeht, restore I the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or 1 declare the associated ADS trip system or ECCS inoperable. l l ACTION 35 - With the number of OPERABLE channels less than required by.the ,

l Minimum OPERABLE Channels per Trip Function requirement l i

a. For one trip system, pl t trip system in the tripped condition within one ho or declare the HPCS system i inoperable.

o b. For both trip systems, declare the HPCS system inoperable.

ACTION 36 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour

• or declare the HPCS system inoperable.

ACTION 37 - With the number of OPERABLE instr ts less than the Minimum I OPERABLE INSTRUMENTS, place th operable instrument (s) in the tripped condition within 1 ho

• or declare the associated emergency diesel generator inop rable and take the ACTION )

required by Specification 3.8.1.1 or 3.8.1.2 as appropriate. '

@TheprovisionsofSpecification3.0.4arenotapplicable.

LA SAlif- unu 2 3/4 3-27 Amendment No.27

INSTRUMENTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION-3.3.4.2 The end-of-cycle recirculation pump trip (E0C-RPT) system instrumenta-tion channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.

ACTION:

a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value,

b. With the number of OPERABLE channels one less than required by the l Minimum OPERABLE Channels per Trip System requirement for one or 1

i. both trip systems, place the inoperable channel (s) in the tripped i condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. i

c. With the number of OPERABLE channels two or more less than required by_ the Minimum OPERABLE Channels per Trip System requirement (s) for one trip system and:

1. If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, c 2. If the inoperable channels include two turbine control valve i channels or two turbine stop valve channels, declare the trip system inoperable.

d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, otherwise, either:

1. Increase the MINIMUM CRITICAL POWER (MCPR) Limiting Condition for Operation (LCO) to the EOC-RPT inoperable value per Speci- '

fication 3.2.3 within the next 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or

2. Reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e. With both trip systems inoperable, restore ut least one trip system to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,

1. Increase the MINIMUM CRITICAL POWER (MCPR) Limiting Condition for Operation (LCO) to the EOC-RPT inoperable value per Speci-fication 3.2.3 within the next I hour, or

2. Reduce THERMAL POWER to less than 30% RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

e provisions of spec 1fication 3.0.4 are not applicable.

LA SALLE - UNIT 2 3/4 3-39 Amendment No. 41

l I

lb '

j

INSTRUMENTAT10N E4.3.7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION

• LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Tabie 3.3.7.1-1 shall be OPERABLE" with their clarm/ trip setpoints within the j specified limits.  ;

APPLICABILITY: As shown in Table 3.3.7.1-1.

ACTION:

a. With a radiation monitoring instrumentation channel alarm / trip setpoint exceeding the value shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable,

b. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.  ;

c. The provisions of Specificatior 0.3 nd 3.0.4 re not applicable.

SURVEILLVCE REQUIREMENTS 4 trA-4.3.7.1 Each of the above required rtdiation monitoring instrumentation ,

channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1.

i l

l "The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defusled.

l l

1 LA SALLE - UNIT 2 3/4 3-57

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION

• j .

LIMITING CONDITION FOR OPERATION ,~

3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-3 sr.all

• be OPERABLE.** j APPLICABILITY: At all times.

ACTION:

a. With one or more seismic monitoring instruments inoperable for more ,

than 30 days, prepare and submit a Special Report to the Commission I l

pursuant to Specification 6.6.C within the next 10 days outlining ,

the cause of the malfunction and the plans for restoring the '

instrument (s) to 0FERABLE status.

12.

b. The provisions of Specificatio 3.0.3(nd3.0garenotapplicable. .

SURVE1LLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be i demonstrated OPERABLE by the performance nf the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown

in Table 4. 3.7.2-3. -

l l 4. 3. 7. 2. 2 Each of the above required seismic monitoring instruments actuated l- during a seit.mic event greater than or ec;ual to 0.02g shall be restored to OPERABLE status within 24 h*urs and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed 'to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared a'nd submitted to the Co'nmission pursuant to Specification 6.6.C within 10 days describing the magnitude, l f requency spectrum, and resultant ef fect uppn unit features important to safety.

• The Seismic Monitoring Instrumentation System is shared between La Salle Unit I and La Salle Unit 2.

• • The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when def ueled.

LA SALLE - UNIT 2 3/4 3-60 Amendment No.11

• I INSTRUMENTATION I METEOROLOCICAL MONITORING INSTRUMENTATION * '

LIMITING CONDITION FCR OPERATION

=

a  !

3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.**

At all times.

^

APPLICABILITY:

ACTION:

L

a. With one or more meteorological monitoring instrumentation channels ie9perable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.C within the next l 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status,

b. The provisions of Specificatio Tenotapplicable.

.0.3kd3.0 t

SURVEILLANCE RE00'.REMENTS 4.3.7.3 Each' of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

"The Meteorological Monitoring Instrumentation System is shared between La Salle Unit I and La Salle Unit 2.

• • The normal or emergency power source may be inoperable in ORERATIONAL CONDITION 4 or 5 or when defueled.

I LA SALLE - UNIT 2 3/4 3-63 Amendment No.11

I f

INSTRUM[NTATION .

TRAVERSING IN CORE PROBE SYSTEM l LIMITING CONDITION FOR OPERATION ,

3.3.,7.7. The traversing in-core probe system shall be OPERABLE with:

a. Movable detectors, drives and readout equipment to map the core in the required measurement locations, and

b. Indexing equipment to allow all required detectors to be calibrated in a common location.

APPLICABILITY: When the traversing in-core probe is used for:

! *a, Recalibration of the LPRM detectors, and "b. Monitoring the APLHGR, LHGR, MCPR, or MFLPD.

ACTION:

a. With one or more TIP measurement locations inoperable, required measure-ments may be performed as described in 1 and 2 below, provided the reactor core is operating in an octant symmetric control rod pattern, and the total core TIP uncertainty for the present cycle has been measured to be less than 8.7 percent.

1. TIP data for an inoperable measurement location may be replaced by data obtained from that string's redundant (symmetric) counterpart if the substitute TIP data was obtained from an operable measurement location.

2. TIP data for an inoperable measurement location may be replaced by l- data obtained from a 3-dimensional BWR core simulator code normalized l with available operating measurements, provided the total number of I ,

simulated channels (measurement locations) does not exceed:

1

' a) All channels of a single TIP machine, or -

b) A total of five channels if more than one TIP machine is involved.

b. Otherwise, with the TIP system inoperable, suspend use of the system for the above applicable monitoring or calibration functions.

J SL are not applicable.

c. The provisions of Specificatiorg 3.0.3 SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to use for the above applicable monitoring or calibration functions.

"Only the detector (s) in the required measurement location (s) are required to be OPERABLE.

LA SALLE - UNIT 2 3/4 3-73 Amendment No. 35 -

t  :

. INSTRUME NT ATION FIRE DETECTION INSTRUMENTATION '

LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection 2one of Unit I and Unit 2 shown in Table 3.3.7.9-1 shall be OPERABLE.*

APPLICABILITY: Whenever equipment protected by the fire detection instrument '

is required to be OPERABLE.

ACTION:

' With the number of OPERABLE fire detection instruments less than the Minimum Instruments OPERABLE requirement of Table 3.3.7.9-1: i

a. Within I hour, establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the primary containment, then inspect the primary containment at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or monitor the containment air temperature at least once per hour at the locations '

listed in Specification 4.6.1.7.

b. Restore the minimum number of instruments to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l pursuant to Specification 6.6.C within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status,

c. The provisions of Specificatio e not applicable.

.0.3 @ 3.0.

SURVE1LLANCE REQUIREMENTS 4.3.7.9.1 Each of the above required fire detection instruments which are >

accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE l

by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN

[ exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months. .

I 4.3.7.9.2 The NFPA Standard 72D supervised circuits supervision associated I with the detector alarms of each of the above required fire detection

} instruments shall be demonstrated OPERABLE at least once per 6 months. Super-I vised circuits with detectors which are inaccessible during unit operation shall '

be demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the previous 6 months.

l *The normal or emergency power source may be inoperable in OPERAT]ONAL CONDITION 4 or 5 or when defueled.

l LA SALLE - Uhli 2 3/4 3-75 Amendment No.11 1

l l

i INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION l

l 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The j

alarm trip setpoints of these channels shall be determined in accordance with  !

the Offsite Dose Calculation Manual (00CM).

l l

APPLICABILITY: At all times.  !

l ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel l alarm / trip setpoint less conservative than required, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. ,

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to '.

OPERABLE status within the time specified in the ACTION or, in lieu of a Licensee Event Report, explain in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified,

c. The provisions of Specifications 3.0.3, . 0. and 6.6.8.2.b are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE ,

CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.10-1.

LA SALLE - UNIT 2 3/4 3-81

~ ._- .-. - _

4 INSTRUMENTATION

, RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITIKi CONDITION FOR OPERATION _

3.3.7.11 ine radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The  ;

alarm / trip setpoints of these channels shall be determined in accordance with '

the ODCM.

APPLICABILITY: As shown in Table 3.3.7.11-1 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required, 1 immediately suspend the release of radioactive gareous effluents monitored by the affected channel or declare the channel inoperable,

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown '

in Table 3.3.7.11-1.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

h.

SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel 5, hall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.11-1. ,

/.

LA SALLE - UNIT 2 3/4 3-86

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.12 The loose part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.6.c within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status, o_

b. The provisions of Specificatio 3.0.3([d3.0.jarenotapplicable.

SURVEILLANCE REQUIREMENTS 4.3.7.12 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of:

a. CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and I

c. CHANNEL CALIBRATION at least once per 18 months.

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1 1

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LA SALLE - UNIT 2 3/4 3-91 l

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3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM l

RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant system recirculation loops shall be in operation.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 ACTION

a. With only one (1) reactor coolant system recirculation loop in operation, comply with Specification 3.4.1.5 and:

1. Within four (4) hours:

a) Place the recirculation flow r.ontrol system in the Master Manual mode or lower, and b) Increase ;..e MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit by 0.01 to 1.08 per Specification 2.1.2, and c) Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Limiting Condition for Operation by 0.01 per Specification 3.2.3, and, d) Reduce the Average Power Range Monitor (APRM) Scram and Rod Block and Rod Block Monitor Trip Setpoints and Allowable Values to those applicable to single recirculation loop operation per Specifications 2.2.1, 3.2.2, and 3.3.6.

(2. The provisions of Specification 3.0.4 are not applicable 2./. Otherwise, be in at least HOT SHUTDOWN within the next twelve (12) hours.

b. Nith no reactor coolant recirculation loops in operation:

1. Take the ACTION required by Specification 3.4.1.5, and

2. Be in at least HOT SHUTDOWN within the next six (6) hours.

LA SALLE - UNIT 2 3/4 4-1 Amendment No. 41

i REACTOR COOLANT SYSTEM k

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THIS PAGE INTENTIONALLY LEFT BLANK i

I 4

I LA SALLE - UNIT 2 3/4 4-2a Amendment No.40

I.

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemis'try of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-Ir APPLICABILITY: At all times.

ACTION:

a. In OPERATIONAL CONDITION 1:

1. With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval and, for conductivity and chloride concen-tration, for less than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, but with the conductivity less than 10 pmho/cm at 25'C and with the chloride concentration less than 0.5 ppm, this need not be reported to the Commission.,

Q ,the provisions oT apecificar. ion 4.v..,

are not applicaDig

2. With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval or, for conductivity and l

chloride concentration, for more than 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per year, be in at least STARTUP within the next 6 hr.a.'s.

3. With the conductivity exceeding 10 pmho/cm at 25'C or chloride concentration exceeding 0.5 ppm, be in at least HOT SHUTDOWN l within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN as rapidly as the cooldown rate limit permits.

l b. In OPERATIONAL CONDITIONS 2 and 3 with the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hcurs,

c. At all other times:

1. With the conductivity er pH exceeding the limit specified in j

Table 3.4.4-1, restore the conductivity and pH to within the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2. With the chloride concentration exceeding the limit specified in Table 3.4.4-1 exceeded for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, perform an engineering evaluation to determine the effects of the out-of-limit condition c0 the structural integrity of the reactor l coolant system. Determine that the structural integrity of the reactor coolant system remains acceptable for continued opera-tion prior to proceeding to OPERATIONAL CONDITION 3.

l

3. The provisions of Specification 3.0.3 are not applicable.

LA SALLE - UNIT 2 3/4 4-11

i i

REACTOR COOLANT SYSTEM i l

3/4.4.7 MAIN STEAM LINE ISOLATION VALVE 5 .

LIMITING CONDITION FOR OPERATION l 3.4.7 Two main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to 3 and less than or '

equal to 5 seconds.  !

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.  !

ACTION: l With one or more MSIVs inoperkble:

1. Maintain at least one MSIV OPERABLE in each affected main steam line that is open and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> either:

I a) Restore the inoperable valve (s) to OPERABLE status, or  !

k b) Isolate the affected main steam line by use of a deactivated 1 MSIV in the closed position. l

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 l and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(b. The provisions of Specification 3.0.4 are not applicabl SURVEILLANCE REQUIREMENTS 4.4.7 EachoftheaboverdquiredMSIVsshallbedemonstratedOPERABLEby verifying full closure between 3 and 5 seconds'when tested pursuant to Specification 4.0.5.

)

i LA SALLE - UNIT 2 3/4 4-22

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REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY l I

LIMITING CONDITION FOR OPERATION - _ _ _ _

l 1

3.4.8 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5. i l

ACTION: J

a. With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above reouirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor 4 Coolant System temperature more than 50'F above the minimum I temperature required by NOT considerations..

b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restors the structural ,

integrity of the affected component (s) to within its limit or )

isolate the affected component (s) prior to increasing the Reactor I Coolant System temperature above 200*F.

c. With the structural integrity of any ASME Code Class 3 component (s) i not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or l isolate the affected component (s) from service.

~

(d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS _, __

4.4.8 No additional'Surve111ance Requirements other than those required by  ;

Specification 4.0.5.  ;

l LA SALLE - UNIT 2 3/4 4-23

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each primary con?.ainment air lock shall be OPERABLE with: '

a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

b. An overall air lock leakage rate of less than or equal to 0.05 L, at P,, 39.6 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

a. With one primary containment air lock door inoperable:

1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within i

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

[ . The provisions of Specification 3.0.4 are not applicable

! b. With the primary containment air lock inoperable, except as a result of no inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be Tn at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in l- COLD SHUT 00WN within'the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I

• See Special Test Exception 3.10.1.  ;

LA SALLE - UNIT 2 3/4 6-5

CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The primary containment isolation valves and the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

' ACTION:

a. With one or more of the primary containment isolation valves shown in Table 3.6.3-1 inoperable:

1.

Maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either; a) Restore the inoperable valve (s) to OPERABLE status, or b) Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,* or c) Isolate each affected penetration by use of at least one '

closed manual valve or blind flanae.*

h) The provisions of Specification 3.0.4 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the affected penetration is isolated in accordance with Action a.1.b) or a.1.c) above, and provided that the associated system is declared inoper-able, if applicable, and the appropriate action statements for that system are performed.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• b.

With one or more of the reactor instrumentation line excess flow ,

check valves shown in Table 3.6.3-1 inoperable: i

1. Operation continue and the provisions of Specificatio 0.3 (ind 3.0.4 Tare not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

' a) The inoperable valve is returned to OPERABLE status, or b) The instrument line is isolated and the associated instrument is declared inoperable.

2. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

" Isolation valves closed to satify these requirements may be reopened on an intermittent basis under administrative control.

LA SALLE - UNIT 2 3/4 6-25 Amendmerst No. 14

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PLANT SYSTEMS l

l 3/4.7.4 SEALED SOURCE CONTAMINATION '

LIMITING CONDITION FOR OPERATION 3 4

3.7.4 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of i alpha emitting material shall be free of greater than or equal to 0.005 micro-curie of removable contamination. l i

APPLICABILITY: At all times. i ACTION:  !

a. With a sealed source having removable contamination in excess of the above limit, withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or )

2. Dispose of the sealed source in accordance with Commission i Regulations.

, b. The provisions of Specificatio@ 3.0.3@d 3.0jare not applicable.

SURVEILLANCE REQUIREMENTS I

4.7.4.1. Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

l a. The licensee, or i

l b. Other persons specifically authorized by the Commission or an l Agreement State.

t The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

, 4.7.4.2 Test Frequencies - Each category of sealed sources, excluding startup l sources and fission detectors previously subjected to core flux, shall be l tested at the frequency described below,

a. Sources in use - At least once per six months for all sealed sources containing radioactive material:

l 1. With a half-life greater than 30 days, excluding Hydrogen 3, i and 1

2. In any form other than gas.

LA SALLE - UNIT 2 3/4 7-9 i

l

l PLANT SYSTEMS 3/4. 7. 5 FIRE SUPPRESSION SYSTEMS 1

FIRE SUPPRESSION WATER SYSTEM 1 LIMITING CONDITION FOR OPERATION 3.7.5.1 The fire suppression water system shall be OPERABLE

• with: 1

a. Two OPERABLE fire suppression diesel driven fire pumps, each with a l capacity of 2500 gpm, with their discharge aligned to the fire sup-  !

pression header, I

b. An OPERABLE flow path capable of taking suction from the CSC5 water tunnel and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm l device on each sprinkler, hose standpipe, and the last valve ahead '

of the deluge valve on each deluge or spray system required to be i OPERABLE per Specifications 3.7.5.2 and 3.7.5.4.

l APPLICABILITY: At all times.  ;

l ACTION: l l

a. With one fire pump and/or one water supply inoperable, restore the I inoperable equipment to OPERABLE status within 7 days or, prepare ['

and submit a Special Report to the Commission pursuant to Specifi-cation 6.6.C within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to  !

OPERABLE status or to provide an 1 ternate backun pump or supply.

The provisions of Specificatio 3.0.3 @ 3.0.j a,re not applicable.

b. With the fire suppression water system otherwise inoperable:

1. Establish a backup fire suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.,

and +

2. Prepare and submit a Special Report in accordance with Specifi- j '.

cation 6.6.C; '

a) By telephone within 24jhours, ,

L b) Confirmed by telegraph, mailgram or facsimile transmission l no later than the first working day following the event, l and c) In writing within 14 days following the event, outlining

'the action taken, the cause of the inoperability and the l plans and schedule for restoring the system to OPERABLE l status. .,

• The normal or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

l l

LA SALLE - UNIT 2 3/4 7-11 Amendment No.11 l

I l

PLANT SYSTEMS  ;

DELUGE AND/0R SPRINKLER SYSTEMS.

LIMITING CONDITION FOR OPERATION  ;

I 3.7.5.2 The deluge and sprinkler systems of Unit I and Unit 2 showrl in Table 3.7.5.2-3 shall be OPERABLE.*

APPLICABILITY: Whenever equipment protected by the deluge / sprinkler systems ,

are required to be OPERABLE.

ACT. I__ON,,:

a. With ont or more of the deluge and/or sprinkler systems shown in Table 3.7.5.2-1 inoperable, within I hour establish a continuous fire watch with bachup fire L.ppression equipment for those areas in t which redundant systems or components could be damaged; for other  ;

areas, establish an hourly fire watch patrol. Restore the system to ,

OPERABLE status within 14 days or, prepare and submit a Special Report l 1

to the Commission pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

O

b. The provisions of Specification 3.0.3hnd 3.gare' not applicable.

SURVEILLANCE REQUIREMENTS l 4.7.5.2 Each of the above required deluge and sprinkler systems shown in Table 3.7.5.2-1 shall be demonstrated, OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct position,

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

c. At least once per 18 months

$

1. By performing a system functional test which includes simulated automatic actuation of the system, and:

a) Verifying that the automatic valves in the flow path actuate to thei" c0rrect positions on a test signal, and b) Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

• The ..ormal or emergency power source may be inoperable in OPERATIONAL COND1110N 4 or 5 or when defueled.

LA SALLE - UNIT 2 3/4 7-14 Amencment No.ll

v PLANT SYSTEMS CO, $Y$TEMS Q MITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO2 systems of Unit 1 and Unit shall be OPERABLE.*

a. Division I diesel generator 0 room,

b. Division 2 diesel generator 2A room.

c. Division 3 diesel generator 2B room. ,

d. Unit 1 Division 2 diesel generator IA room.

AoPLICABILITY: Whenever equipment protected by the low pressure CO2 systems is required to be OPERABLE. .

ACTION:

a. With one or more of the above required low pressure C0 systems inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant

-systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, prepare and submit a $pecial Report to the l Commission pursuant to specification 6.6.C within the next 30 days outlining the action taken, the cause of the incperability and the plans and schedule for restoring the system to OP RABLE status,

b. TheprovisionsofSpecification3.0.3{d3.0 re not applicable.

$URVEILLANCE REQUIREMENTS l

4.7.5.3 Each of the above required low pressure C0 systems shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying C02 storage tank level to be greater than 50% full and pressure to be greater than 290 psig, and

b. At least once per 31 days by verifying that cach valve (tr.anual, pomer-operated, or automatic) in the flow path is in the correct position.

c. At least once per 18 months by verifying:

1. The system valves and associated motor operated ventilation dampers actuate, manually and automatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test."

• The normal ei emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 2 3/4 7-17 Ame.adment No.11

- - - _.-____-___________d

. PLANT $YSTEMS .

FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION e W

3.7.5.4 The fire hose stations of Unit I and Unit 2 shown in Table ( 3.7.5.4-3 shall be OPERABLE.

• APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION: '

a.

With one or more of the fire hose stations shown in Table 3.7.5.4-1 inoperable, route an additional fire hose of equal or greater diameter to the unprotected area (s)/ zone (s) from an OPERABLE hose station within I hour if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  !

Restore the inoperable fire hose station (s) to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission l; pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

D

b. The provisions of Specificatio 3.0.q( nd 3.0.4)are not applicable. l SURVE!LLANCE RE0VIREMEN15 r

4.7.5.4 Each' of the above required fire hose stations shown in Table 3.7.5.4-1 shall be demonstrated OPERABLE: ,

4. At least once per 31 days by a visual insperiion of the fire hose g

stations accessible during plant operation so assure all required equipment is at the station.

b. At least once per 28 months by:

1. Visual inspection of the fire hose stations not accessible during plant operation to assure all required equipment is at the station.

2. Removing the hose for inspection and reracking', and

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings,

c. At least once per 3 years by partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

d. Within 5 years and between 5 and 8 years af ter purchase date and at least every 2 years thereafter by conducting a hose hydrostatic test at a pressure of 250 psig or at least 50 psig above the maxinum fire main operating pressure, whichever is greater.

LA SALLE - UNIT 2 3/4 7-18 Amendment No.1I

PLANT $YST[M$

]

t 3/4.7.6 FIRE RATED A$$EMBLIES l

LIMITING CONDITION FOR OPERATION k

3.7.6 All fire rated assemblies, including walls, floor / ceilings ' cable tray I

enclosures and other fire barriers separating safety-related fire areas or l separating portions of redundant systems irnportant to safe shutdown within a l l

fire area, and all sesling devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable and piping penetration seals and i ventilation seals) shall be OPERABLE.

APPLICABILITY: At all times. I l

L ACTION.

1

a. With one or more of the above required fire rated assemblies and/or I sealing devices ineperable, within I hour either establish a con-tinuous fire watch on at least one side of the affected assembly (s) ]

and/or device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and/or sealing device (s) and establish an hourly fire watch patrol. Restore the inoperable i fire rated assembly (s) and/or sealing device (s) to OPERABLE status '

within 7 days or, prepare and submit a Special Report to the Commission l pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoperable fire rated assembly (s) and/or sealing device (s) and plans and schedule for restoring the fire rated assembly (s) and/or sealing device (s) to OPERABLE status.

A,

b. The provisions of Specificatio 3.0.3{d3.0.jarenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.6.1 Each of the above required fire rated assemblies and sealing devices shall be verified to be OPERABLE at least once per 18 months by performing a visual inspection of:

a. The exposed surface. mf each fire rated assemblies.

I b. Each fire wincow/ fire damper and associated hardware.

c. At least 10% of each type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penetration shall be made.

This inspection' process shall continue until a 30% sample with no apparent changes in appearance or abnormal degradation is found.

l LA SALLE - UNIT 2 3/4 7-23 Amendment No.11

I i

PLANT SYSTEMS ,

3/4.7.10 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.10 The main turbine bypass system shall be OPERABLE. I APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER. l i

ACTION. , i

a. With the main turbine bypass system inoperable: i

1. If at least four bypass valves are capable of accepting steam t flow per Surveillance 4.7.10.a:  !

l

a. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either:

1) Restore the system to OPERABLE status, or

2) Increase the MINIMUM CRITICAL POWER RATIO (MCPR)

Limiting Condition for Operation (LCO) to the main  ;

turbine bypass inoperable value per Specification 3.2.3. l

1. b. Otherwise, reduce THERMAL POWER to less than 25% of RATED l

THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

! 2. If less than four bypass valves are capable of accepting steam I

flow per Surveillance 4.7.10.a: 3 l

a. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, increase the MCPR LCO to the main turbine  !

bypass inoperable value per Specification 3.2.3, and )

b. Within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, restore the system to OPERABLE status, l

c. Otherwise, reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. i The. provisions of 5pectrication 3.0.4 are not applicab SURVEILLANCE REQUIREMENTS 3 l

4.7.10 The main turbine bypass system shall be demonstrated OPERABLE at least  !

l once per: j

a. 7 days by cycling each turbine bypass valve through at least one i

complete cycle of full travel.

b. IB months by:

i 1. Performini a system functional test which. includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.

L 2. Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less i than or equal to 200 milliseconds.

LASALLE - UNIT 2 ,

3/4 7-34 Amendment No. 41 l 1

l ELECTRICAL POWER SYSTEMS  !

PRIMARY CONTAINMENT PENETRATION , CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.2 All primary containment penetration conductor overcurrent protective i devices shown in Table'3.8.3.2-1 shall be OPERABLE. .

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION: l With one or more of the primary containment penetration conductor l overcurrent protective devices shown in Table 3.8.3.2-1 inoperable, i restor'ethe protective device (s) to OPERABLE status or de-energize '

the circuit (s) by tripping the associated circuit breaker or racking  !

out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the 4--- circuit breaker to be tripped or the inoperable circuit breaker

, racked out, or removed, at least once per 7 days thereafter. 1 Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and  !

in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.  !

Fb. The provisions of Specification 3.0.4 are not applicable to over- '

i l

current devices in circuits which have their circuit breakers tripped.

racked out, or removed.

SURVEILLANCE REQUIREMENTS 1

l 4.8.3.2 Each of the primary containment penetration conductor overcurrent )

protective devices shown in Table 3.8.3.2- 1 shall be demonstrated OPERABLE: )

a. At least once per 18 months: ,

l

1. By verifying that the 6.9 kV and 4.16 kV circuit breakers I are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:

a) A CHANNEL CALIBRATION of the associated protective relays, and

]

b) An integrated system functional test of the breakers 1 overcurrent protective trip circuit which includes simulated automatic actuation of the trip system to demonstrate that the overall penetration protection design remains within operable limits, c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found-or all circuit breakers of that type have been functionally tested. j LASALLE - UNIT 2 3/4 8-22 Amendment No. 23

)

i i

l ELECTRICAL POWER SYSTEMS l

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION I LIMITING CONDITION FOR OPERATION l

3.8.3.3 The thermal overload protection of each valve shown in Table 3.8.4.2-1  !

shall be bypassed continuously or under accident conditions, as applicable, by an OPERABLE bypass device integral with the motor starter. I APPLICABILITY: Whenever the motor operated valve is required to be OPERABLE.

1 ACTION:

a With the thermal overload protection for one or more of the above I required valves not bypassed continuously or under accident conditions,  ;

as applicable, by an OPERABLE integral bypass device, take administra- '

+ tive action to continuously bypass the thermal overload within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s)'for the affected system (s).

. The provisions of Specification 3.0.4 are not applica SURVEILLANCE REQUIREMENTS 4.8.3.3.1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device by the performance of a CHANNEL FUNCTIONAL TEST of the bypass circuitry for those thermal overloads which are normally in force during plant operation and bypassed under accident conditions and by verifying that the thermal overload protection is bypassed for those thermal overloads which are continuously bypassed and temporarily placed in force only when the valve motors are undergoing periodic or maintenance testing:

a. At least once per 18 months, and

b. Following maintenance on the motor starter.

4.8.3.3.2 The thermal overload protection for the above required valves which are continuously bypassed shall be verified to be bypassed following testing during which the thermal overload protection was temporarily placed in force.

i l

LA SALLE - UNIT 2 3/4 8-26

l RADIDACTIVE EFFLUENTS l

. . . . . DOSE l LIMITING CONDITION FOR OPERATION $ fl 3.11.3.2 The dose or dose commitment to an individual from radioa6tive materials in liquid ef fluents released, from each reactor unit, f rom the site (see Figure 5.1.1-1) shall be limited:

l

a. During any calendar quarter to less than or equal to 1.5 mrem to the i total body and to less than or equal to 5 mrem to any vrgan, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times. j ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of 1 any other report required by Specification 6.6.A, prepare and submit l to the Commission within 30 days, pursuant to Specification 6.6.C. a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce <

the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent three calendar quarters, so that the cumulative dose or dose commit-ment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include the radiological impact on finished drinking' water supplies at the nearest downstream drinking water source.

b. The provisions of Specificatio 3.0.3h3.0Jalenotapplicable.

SURVEILLANCE REQUIREMENTS

! 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents

( shall be determined in accordance with the ODCM at least once per 31 days, l

l o i

I LA SALLE - UNIT 2 3/4 11-6 Amendment No.11

I

]

l RADIDACTIVE EFFLUENTS

. . . LIQUID WASTE TREATMENT SYSTEM LIM) TING CONDITION FOR OPERATION

}

3.11.1.3 The liquid radweste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive j materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from each reactor unit, from the site (see Figure 5.1.1-1), when averaged over 31 days, would exceed 0.06 mr'em to the i total body or 0.2 mrem to any crgan, j APPLICABILITY: At all times. l

. l ACTION:

]

a. With the liquid radweste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment end in excess of the above limits, in lieu of any other report required by Specification 6.6. A. prepare and submit to the l Commission within 30 days pursuant to Specification 6.6.C a Special Report which includes the following information: ]

1. Identification of the inoperable equipment or subsystems and the reason for inopernbility, j i

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence. I

b. The provisions of Specificatio 0.3 are not applicable.

SURVEILLANCE REQUIREMENTS i

4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the ODCM.

4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 30 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.

I LA SALLE - UNIT 2 3/4 11-7 Amendment No.11

i RADI0 ACTIVE EFFLUENTS  !

LIQUID HOLDUP TANKS ,

LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary r tanks shall be limited to less than or equel to the limits calculated in the ODCM.

I l

l APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b. The provisions of Specificatio 3.0.3 re net applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

l LA SALLE - UNIT 2 3/4 11-8 e

r- j I

l l

1 RADIDACTIVE EFFLUENTS

, , , DOSE - NDBLE GASES '

)

LIMITING CONDITION FOR OPERATION  :

1 1

3.11.2.2 The air dose due to noble gases released in nach reactor unit, from the site (see Figure 5.1.1-1) gaseous shall beeffluents, limited tofrom the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.  :

APPLICABILITY: At all times.

l ACTION:

I- a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.6. A, prepare and submit to the j Commission within 30 days, pursuant to Specification 6.6.C, a .

Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. .

b. The provisions of Specificatio . 0.3 Qd 3. 0.4 re not applicable.

SURVEILLANCE REQUIREMENTS 1

4.11.2.2 Dese Calculations Cumulative dose contributions f9r the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

LA SALLE - UNIT 2 3/4 11-13 Amendment No.11 1

l

t

, PAD 10 ACTIVE EFFLUENTS

. ... DOSE - RAD 1010 DINES, RADIOACTIVE MATERI ALS IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NDBLE GASE5 t

LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiciodines and radioactive materials in particulate form, and radionuclides, other than noble gases, with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1.1-1) shall be limited to the following: *

a. During any calu.dar quarter: Less than or equal to 7.5 mrems to any organ, and-

b. During any calendar year

Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioiodines, radioactive >

l materials in particulate form, or radionuclides (other inan noble is gases) with half-lives greater than 8 days, in gaseous effluents l exceeding any of the above limits, in lieu of eqi other report

! required by Specification 6.6. A, prepare and suDmit to the l Commission within 30 days, pursuant to Specification 6.6.C, a o

Special Report which identifies the cause(s) for exceeding the limit l and defines the corrective actions that have been taken to reduce the l-releases and the proposed corrective actions to be taken te assure that subsequent releases' will be in compliance wg the above limits.

b. The provisions of Specificatio .0.3h3.0.4)renotapplicable.

l- SURVEILLANCE REOUIREMENTS

( _

4.11.1.3 Dose Calculations Cumulative dose contributions for the current l- calendar quarter anc current calendar year shall be determined in accordance with the ODCM at least once per 31 days.'

s.

I l

l LA SALLE - UNIi 2 3/4 11-1A /ceadment No.11 l

l:

we w

'k I RADIDACTIVE EFFLUENTS

,,,, GASEOUS RADWASTE TREATMENT SYSTEM ,.

LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser air ejector system is in operation.

IC,

• ACTION:

a. With the GASEOUS RADWASTE TREATMENT SYSTEM inoperable for more than 7 days, in lieu of any other report required by Specification 6.6. A, j prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

! 2. Action (s) taken to restore the inoperable equipment to OPERABLE ,

! status, and

3. Summary description of action (s) taken to prevent a recurren:e.

b. The provisions of Specificatioq( 3.0.3 ffd 3.0.f)are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM shall be verified to be in operation at least once per 7 days.

LA SALLE - UNIT 2 3/4 11-15 Amendment No.ll

_ . __ _ _ _ ~~

?

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM l- l

j. LIMITING CONDITION FOR OPERATION L  ;

l.

3.11.2.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM ,

shall be OPERABLE and be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from each reactor unit, from the site (see Figure 5.1.1-1), when averaged over 31 days, would exceed 0.3 mrem to any organ.

I APPLICABILITY: At all times.

ACTION:

l a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable fot more than 31 days, or with gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specification 6.6.A, prepare and submit l to the Commission within 30 days, pursuant to Specification 6.6.C, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 1

l 2. Action (s) taken to restore the inoperable equipment to OPERABLE l

status, and 1

!. 3. Summary description of action (s) taken to prevent a recurrence.

t x.

b. The provisions of Specificatio 3.0.3 re not applicable.

L SURVF LANCE REQUIREMENTS 4'.11.2.5.1 Doses due to gaseous releases from the site shall be projected at l

least 'ce per 31 days in accordance with the ODCM.

4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 30 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous

, 92 days.

LA SALLE - UNIT 2 3/4 11-16 Amendment No.11

RADI0 ACTIVE EFFLUENTS

. EXPLOSIVE GAS MIXTURE LIMITING CONDITION-FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.

APPLICABILITY: Whenever the main condenser air ejector system is in operation.

ACTION:

a. With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

A

b. The provisions of Specificatio 3.0.3(Erici 3 0 j)are not applicable.

l l

SURVEILLANCE REQUIREMENTS 1

l 4.11.2.6 -The concentration of hydrogen in the mnin condenser offgas treatment i

system shall be determined to be within the above limits as required by Table 3.3.7.11-1 of Specification 3.3.7.11.

l '

l

}

t LA SALLE UNIT 2 3/4 11-17 1

1 i

i. RADIOACTIVE EFFLUENTS L VENTING OR PURGING-

• LIMITING CONDITION FOR OPERATION l

,; 3.11.2.8 VENTING or PURGING of the containment drywell shall be through the Primary Containment Vent and Purge System or the Standby Gas Treatment System.

~

(-- APPLICABILITY: Whenever the drywell is vented or purged.

i 1

ACTION: 1 l

' a. With the requirements of the above specification not satisfied, )

suspend all-VENTING and PURGING of the drywell.

-b. The provisions of Specificatio . 0. 3 nd 3.0.4 are not applicable.

l l

4 SURVEILLANCE REQUIREMENTS l

4.11.2.8.1 The containment drywell shall be determined to be aligned for VENTING or PURGING through the Primary Containment Vent and Purge System or the Standby Gas Treatment System within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior 'to start of and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during VENTING or PURGING of the drywell.

l . 4.11.2.8.2 Prior to use of the Purge System through the Standby Gas Treatment  ;

System in OPERATIONAL CONDITION 1, 2 or 3 assure that: l

a. Both Standby Gas Treatment System trains are OPERABLE, and o b. Only one of the Standby Gas Treatment System trains is used for l- PURGING.

l LA SALLE - UNIT 2 ,

3/4 11-19

('

RADIDACTIVE EFFLUENTS 3/4.11.3 SOLID RADIDACTIVE WASTE LIMITING CONDITION FOR OPERATION  !

'l 3.11.3 The solid radwaste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging.

of radioactive wastes to ensure meeting-the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times. I ACTION: )

a. With the packaging requirements of 10 CFP Part 20 and/or 10 CFR

Part 71 not satisifed, suspend shipment 6 of defectively packaged i solid radioactive wastes from the site,

b. . With the solid radwaste system inoperable for more than 31 days,

in lieu of any other report required by Specification 6.6.A, prepare and submit to the Commission within 30 days, pursuant to l Specification 6.6.C, a Special Report whicn includes the following information

1

1. Identification of the inoperable equipment or subsystems and I the reason for inoperability, 1

2. Action (s) taken to restore the inoperable equipment to OPERABLE I status, -

i

3. A description of the' alternative used for SOLIDIFICATION and i packaging of radioactive wastes, and.

4. Summary description of action (s) taken to prevent a recurrence.

t' l' c. The provisions of Specificatio 0.3 are not applicable.

i SURVEILLANCE REQUIREMENTS J

l 4.11.3.1 The solid radwaste system shall be demonstrated OPERABLE at lecst

! once per 92 days by:

a. Operating the solid radwaste system at least once in the previous 92 days in accordance with the Process Control Program, r

b. Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

LA SALLE - UNIT 2 3/411-h0 Ar.endment No.11

i RADIDACTIVE EFFLUENTS

. . . . 3/4.11.4 TOTAL DOSE LIMITING CONDITION FOR'0PERATION

?

-3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fLei cycle sources shall be limited to less than or equal to 25 mrem to the total body or eny organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. .

APPL 1CAML*T h it C # iitos.

ACTION *. .

o

u. 4 ", c ,culate.". doses f t Sm the release of radioactive piat*riebs in lic :d or ga5 A ? Jf +en' ~ ' <ceeding twice the limits of Spid fim t~ons e.l..'i. 2.o 3 1 ) . L. , ; . .'1. 2. 2. a , 3.1L 2. 2. b . 3.11. 2. 3 a a r

. A.2.3.n, in 'ileu of any .'*.her Wort requir.id by Specificatio,'

6.6. A, prepar* W t,ubmit, nursuant to Specification 6.6.C. a j

$p':;al Report to the "irector, Nuclear Reactor Pegulation, U.S.

4: lear Regulatory CommN'on, mhington, D.C. 20555, within 30 d.y , shir.h defines te; <.orrsctive action to be taken to reduce subsqurit raleases to prstent recurrance of exceeding the limits of Specification 3.11.4. This Special Raport shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluents pathways and direct radiation) for a 12 consecutive month period that includes the release (s.) covered by this report. If the esti-mated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of 6 190.11. Submittal of the report is considered a timely request, and a variance is granted until staff action-on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed in other sections of this technical specification, c.

b. The provisions of Specificatio 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculatin m CumA ative dose contributions from liquid and gaseous effluents she x m3 : W in accordance with Specifications 4.11.1.2, 4.11. 2. 2, and 4.11. ! ? . N in ac.tr? nce with the ODCM.

i LA SALLE - UNIT 2 3/4 11-22 Amendment No.11

l 1

i l

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING

~ ~ ~

3/4.12.1 MONITORING PROGRAM-I LIMITING CONDITION FOR OPERATION h 3.12.1. The radiological environmental monitoring program shall be conducted l  !

as specified'in Table 3.12.1-1. j i

APPLICABILITY: At all times. l ACTION: .

a. With the radiological environmental monitoring program not being l conducted as specified in Table 3.12.1-1, in lieu of any other l report required by Specification 6.6. A, prepare and submit to the l l Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the ,

plans for preventing a recurrence. I

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels in Table 3.12.1-2 when averaged over any calendar quarter, in lieu of any other report required by Specifi-cation 6.6.A', prepare and submit to the Commission within 30 days i from the end of the affected calendar quarter a Special Report pursuant to Specification 6.6.C. When more than one of the radio-nuclides in Table 3.12.1-2 are detected in the sampling medium, this J report shell be submitted if:

concentration (1) , concentration (2) + ***> 1.0 limit level (1) limit level (2) -

When radionuclides other than those in Table 3.12.1-h are detected )

and are the result of plant effluents, this report shall be submitted l if the potential annual dose to an individual is equal to or greater I than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 i and 3.11.2.3. This report is not required if the measured level of  ;

radioactivity was not the result of plant effluents; however, in i such an event, the condition shall be reported and described in the l Annual Radiological' Environmental Operating Report. ,

i

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, in lieu of any other report required by Specification 6.6. A, prepare and submit l 1 to the Commission within 30 days, pursuant to Specification 6.6.C, a i Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples.

The locations from which samples were unavai.lable may then be deleted i from those required by Table 3.12.1-1, provided the locations from l which the replacement samples were obtained are added to the environ- I mental monitoring program as replacement locations.

d. Tne provisions of Specificatio are not applicable. )

.0.3 h 3.0 LA SALLE - UNIT 2 3/4 12-1 AmenJment No.11

p  ;

l J

l RADIOLOGICAL ENVIRONMENTAL MONITORING  !

i

• '~ ~ 3/4.12. 2 LAND USE CENSUS  !

k I LIMITING CONDITION FOR OPERATION ) 1 T

-3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal and the nearest residence in each of the 16 meteor-ological sectors within a distance of five miles. (For' elevated releases as l defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals in each of the 16 meteoro-  !

logical sectors within a distance of three miles.)

APPLICABILITY: At all times.

I ACTION: .

i l

a. With a land use census identifying a location (s) which yields a  !

p calculated dose or dose commitment greater than the values currently I being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.6.A, prepare and submit to the Commission within 30 days, prusuant to Specification 6.6.C., a lli Special Report which identifies the new location (s). l 1

l b. With a land use census identifying a-location (s) which yields a j calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently  :

being obtained in'accordance with Specification 3.12.1, in lieu of any other report required by Soecificetion 6.6A, prepare and submit to . l

, the Commission within 30 days, pursuant to Specification 6.6.C., a l Special Report which identifies the new location. The new location ,

shall be added to the radiological environmental monitoring program '

within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment (via the same exposure pattway) may be deleted from this monitoring program after,(October 31) of the year in which this land use census was conducted.' '

c. The provisions of Specificatio s 3.0.3 fnd 3.0gare not applicable.

1

• 1

' SURVEILLANCE REQUIREMENTS L 4.12.2 The land use census shall be conducted at least once per 12 months l between the cates of (June 1 and October 1) using that information which will

provide the best results, such as by a door-to-door survey, aerial survey, or 1- by consulting local agriculture authorities.

l l:

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1 LA SALLE - UNIT 2 3/4 12-9 Amendment No.11

..t RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICARILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taien to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.

b. . The provisions of Specificatior 0.3 e not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 A sumr.ary of the results obtained as part of the above required Inter-laboratory Comparison Program and in accordance with the 00CH (or participants in the EPA crosscheck program shall provide the EPA program code designation for the unit) shall be included in the Annual Radiological Environmental Operating Report.

LA SALLE - UNIT 2 3/4 12-10

l App M P^'"  !

l 3/4.0 APPLICABILITY  ;

i BASES  ;

The specificaticas of this section provide the general equirements ,,

ap icable to each of the Limiting Conditions for Operatio and Surveillance  ;

Requ ements within Section 3/4. In the event of a disag eement between '

the re 'trements stated in these Technical Specificatio and those stated in an ap icable Regulation or Act, the requirements s ted in the applicable Regulation r Act, shall take precedence and shall be et. .

3.0.1 is specification states the applicabi ty of each specification I in terms of de ed OPERATIONAL CONDIT!0N or other specified applicability condition and is ovided to delineate specifical y when each specification is applicable.

3.0.2' This spec ication defines those nditions necessary to constitute compliance with the te of an individual L iting Condition for Operation and associated ACTION req 'rement.

3.0.3 This specificati delineates he measures to be taken for circumstances not directly prov(ded for n the ACTION statements and whose occurrence would violate the inttet of he specification. -For example, Specification 3.7.2 requires two & t i room and auxiliary electric equipment room emergency filtration trains to OPERABLE and provides explicit ACTION requirements if one train is inoper bl . Under the requirements of Specifica-L tion 3.0.3, if both of the requir tra s'are inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> measures must be initiated to p1 e the u it in at least STARTUP within the

~

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least HOT S TDOWN wit n the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the subs uent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> As a further example, Specification 3.6.6.1 requir two primary co inment hydrogun recombiner systems to be OPERABLE and ovides exC icit AC N requirements if one recombiner system is inope ble. Under the requi ents of Specification 3.0.3, if both of the required s tems are inoperable, wit n 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> measures must be' initiated to place th unit in at least STARTUP wi in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and l in et Mast HOT SHUTD0 within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. It is acceptable to l initiate and complete reduction in OPERATIONAL CONDITI S in a shorter time interval than requir d in the ACTION statement and to add e unused portion of this allowable t-of-service time to that provided for o eration in sub-sequent lower OPE TIONAL CONDITION (S). Stated allowable out of-service times

! are applicable r gardless of the OPERATIONAL CONDITION (S) in w ch the inopera-i, bility is disc ered but the times provided for achieving a CON TION l reduction are et applicable if the inoperability is discovered i a CONDI-l TION lower t an the applicable CONDITION.

3.0.4 This specification provides that entry into an OPERATIONA CONDlHON must be m e with (a) the full comple m t of required systems, equipmen or componen OPERABLE and (b) all other parameters as specified in the Lim ing Conditio s for Operation being met without regard for allowable deviations nd out of ervice provisions contained in the ACTION statements.

T e intent of this provision is to ensure that unit operation is not initi ted with either required equipment or systems inoperable or other limits bei exceeded.

LA SALLE - UNIT 2 B 3/4 0-1

APPLICABILITY BASES N ptions to this provisian W;: h proviaed for a-Mm%d a" d specifi Ucntwho tertt4Tth inoperable equipment would not affect plant safety. xceptlohrarutaQin the ACTION statements of the appropriate cations.

3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION state-ments for power scarces, when a nortual or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperable becauto its normal or emergency power source is inoperable and a system, subsystem, train, <

component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components or devices to be .

consistent with the ACTION statements of the associated electrical power I source. It allows operation to be governed by the time limits of the AC1 ION statement associated with the Limiting Condition for Operation for-the normal 1 or emergency power source, not the individual ACTION statements for each system, '

subsystem, train, component or device.that is determined to be inoperable solely j because of the inoperability of its normal or emergency power source. The pro- )

visions of Specification 3.0.5 are not applicable to the HPCS system, electrical l division 3 or diesel generator 18. l Fnr example, Specification 3.8.1.1 requires in part that emergency diesel )

-generators 0 and 2A be OPERABLE. The ACTION statement provides for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i out-of.-service time when emergency diesel generator 0 or 2A is not OPERABLE. 1 If the definition of OPERABLE were applied without consideration of I Specification 3.0.5, all systems, subsystems, trains, compomnts and devices ,

supplied by the inoperable emergency power source, diesel generator 0 or 2A, I would also be inoperable. This would dictate invoking the app dcable ACTION i statements for each of the applicable Limiting Conditions for Op e ation. l However, the provisions of Specification 3.0.5 permit the time lir.ie ' - l continued operation to be consistent with the ACTION statement fo W I ir.cperable emergency diesel generator instead, provided the otror m cified c m ditions are satisfied. In this case, this would mean that the corresponding normal power source must be OPERABLE, and all redundant systems, sub:ystems, trains, components, and devices must be OPERABLE, or otherwise satisfy l Specification 3.0.5 (i.e. , be capable of performing their design function and 1

-have at least one normal or one emergency power source OPERABLE). If they are L not satisfied, action is required in accordance with this specification. ,

As a further example, Specification 3.8.1.1 requires in part that two physically l

> independent circuits between tha offsite' transmission network and the onsite i L Class IE distribution system be OPERABLE. The ACTION statement provides a  !

2a hour out-of-service time when both required offsite circuits are not OPERABLE. 1 If the definition of OPERABLE were aoplied without consideration of Specifica- J tion 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsite circuits, would 1

also be inoperable. This vould dictate invoking the applicable ACTION state-ments for each of the appMuple LCOs. However, the provisions of Specifica- )

tion 3.0.5 permit the time limits for continued operation to be consistent I with the ACTION statement for the inoperable normal power sources instead, provided the other specified conditions are satisfied. In this case, this would mean that- for one division the emergency power source must be OPERABLE LA SALLE - UNIT 2 8 3/4 0-2

APPLICABILITY BASES

.3.0.5 (Continued)

(as must be the components supplied by the emergency power source) and all redundant. systems, subsystems, trains, components and devices in the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e. , be '

capable of performing their design functions and have an emergency power source OPERABLE). In other words, both emergency power sources 0 and 2A must be OPERABLE and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE. If these conditions are not satisfied, action'is required in accordance with this specification.

In OPERATIONAL CONDITION 4 or 5, Specification 3.0.5 is not applicable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation in these OPERATIONAL CONDITIONS must be adhered to.

4.0.1 This specification provides that surveillance activities cessary ensure the Limiting Conditions for Operation are met and will b performed d ng the OPERATIONAL CONDITIONS or other conditions.for which e Limiting Con ions for Operation are applicable. Provisions for add onal surveillance activi es to be performed without regart' to the applicabl PERATIONAL CONDI-rIONS r x ther conditicas are provided in the individual urveillance Require-me r.t s . S veillance Requirements for'Special Test Ex tions need only be performed W n the Special Test Exception is being lized as an exception to an individual ecification.

4.0.2 The prov ions of chis specific ion provide allowable tolerances for performing surveil ce activities be nd those specified in the nominal surveillance intarval. 'se tolerance are necessary to provide operational flexibility because of sche ling and erformance considerations. The phrase "at least" associated with a vei ance frequeru does not negate this allowable tolerance; instead, it rmits the more frequent performance of surveillance activities.

The allowable tolerance for performing ' veillance activities is sufficiently restrictive to ensure th the reliability ssociated with the surveillance activity is.not signif* antly degraded beyon that obtained from the nominal surveillance interva . It is not intended tha the allowable tolerance be used as a convenie e to repeatedly schedule the rformance of surveillances at the allowable olerance limit.

4.0.3 T provisions of this specification set for the criteria for determinatio of compliance with the OPERABILITY requiremen of the Limiting Conditions or Operation. Under this criteria, equipment, syhems or components are assum to be OPERABLE if the associated surveillance activ1Jes have been satisfac'orily performed within the specified time interval. Noth in this provis' n is to be construed as defining equipment, systems or compon ts OPERA E, when such items are found or known to be inoperable although . ill mee ng the Surveillance Requirements.

A SALLE - UNIT 2 B 3/4 0-3 AMENDMENT NO. 50 w

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i APPLICABILITY

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4. 4 This specification ensures that surveillance activities ssociated with a L iting Conditions for Operation have been performed withi the

-specified ime interval prior to entry into an applicable OPERATI AL CONDITION o other specified applicability condition. The inte of this provision is ensure th6t surveillance activities have been tisfactorily demonstrated o a current basis as required to meet the OPERA LITY requirem u ts of e Limiting Condition for Operation. j Under the term of this specification, for example, ring initial plant startup or following- tended plant outage, the applicab e surveillance activities must be per rmed within the stated surveili nce interval prior to placing or returning'the stem or equipment into GPE BLE status. )

4.0.5 This specification nsure; that inser ice inspection ASME Code l Class 1, 2 and 3 components and nservice testi of ASME Code Class 1, 2 and i 3 pumps and valves will be perfor d in act.ord nce with a t aiodically updated version of Section'XI of the ASME iler and ressure vessel Code and Addenda as required by 10 CFR 50, Section 50. Sa. lief from any of the above rquirements has been provided in writ' g y the Commission and is not a part cf these Technical. Specifications.

This specification includes a el ifi (tion of the frequencies of performing the inservice inspection d testXpg activities required by l Section XI of the ASME Boiler and P assure Vestel Code and app'iicable Addenda.

This clarification is provided to nsure consisl  ;

throughout these Technical Speci cations and to\ency in surveillance intervals j

emove any ambiguities relative to the frequencies for erforming the req ired inservice inspection j and testing activities. 1' under the terms of th specification, the more r strictive requirements of the Technical Specifi ionstakeprecedenceoverthkASMEBoilerand 1 Pressure Vessel Code an applicable Addenda EFor exampid the requirements of Specification 4.0.4 t perform surveillance. activities pr r to entry into an OPERATIONAL CONDITIO or other specified applicability cond tion takes precedence over th ASME Boilar and Pressure Vessel Code provision which i

' allows pumps to b tested up to one week after return tu normal operation, j L And for example /the Technical Specification definition of OPER&BLE does nnt grant, a grace feriod before a device that is not capable of perfgrming its l

l Boiler and [, ressure Vessel provision which allows a valve to be iriqapable ofspe I 1 performi its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being d clared i inoper e. ,

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• U y $y'N , Sosci ficat ions- - 3. 0.'11 throuch 3. 0. 4 ' establish the generall _ requirements; Mg $ applicable to_ the Limiting; Conditions for Operation.D i These requirements 'are .

c g'.M l(based y % the ; requirements Ofor)1then Limiting 1 Conditions for_ Operation,':as R R - L istated un1the Code of Federal. Regulations,L-10 CFR: 50.36(c)(2): 7 NWa ' + ' '

ye ; u n3 2 [ELimiting / Conditions" J for Operat f on_ are the T1owest1funct tonal capability: -

j,%+ g gon=performgye;levelstof equiproent required for safe?Toperationi of;Jthe 'E AM1 (g ~f gfacilityh TWhen ka Limiting-Condition for Operation-of a nuclear reactorj m;:p 7; _ =

.isinot: met,atne licensee shall -shutt-down ther reactor or_ follow :any; _ Y U+> irem;ediali acti.ont permittedh byJthei technical Lspecification until~the! -

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eachiindividuals specification,_ as the' requirment i for 2 when _ . (1.e. ,- in, which-d /M TOPERATIONAL CONDITIONS Jor.cother s specifiede CONDITIONS) = conformance lto, th' eI

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iLimiting ConditionsfforiOperatlon, is- required? for safe' operationi ofL.the_-

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, . facility.1 LThe1 ACTION ' requirements establish those remedial . measures thati must? '

ibejtaken 'within specified;timeflimits,,~when 'the: requirementsc of' a Limiting (

?[ ik: w w jgnditioni for : Operation lis Mnot 3 ! met.9;It is not Intended. that the sh'utdown!

f O e :_ACTIONLrequirements be Quseds ts en operational Econvenience >which: permits g6  ;(routine)Jx,voluntarybremoval of a' system (s) or component (s)4from service !ini Gw lieu of other alternatives that,would not- resulti in -redundant systems mors Mi se 1  : compcnents :being < inoperable.-

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1There:are two!b ib types o_f ACTION req'uirements. ,The .first Lspecifies=3 the

& ' "p" 1 f 9emedlWmeasures thate permit continued operation of Lne facility which ;1s~not- '

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lfurthenicestricted by the time 11mits of-the ACTION; requiremens.- - In" this-un . case,c conformancen to the ACTION- requirements provides an acceptable leveliof'  ;

LBM "safetylfor? unlimited continued operation'as longcas'ithe ACTIONi requirements-W i

[ co;ntinuei to C be j met (.The second type:of. ACTION requirement specifles a. time J04

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flimitpin_ which conformance to'the conditions oflthe Limiting..Conditiens_~ forJ

,7 0pe. ration;Jmustg be; met.. iThis- time--limit .is'the' allowable; outage time-to  :;

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[restoreLan' inoperable system or,componentcto OPERABLE status;or for restoring gparameters:withinLepecified limits. if tMse actions arei not completed within

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the allowable outage time limics,;a shutdown'is required to place the1acility fin W OPERATIONAL CONDITION or other specified CONDITION in which the.

F@ Especification no longer applies,

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0 kh ,y 3 , OThe(specified time limits of the ACTION recuirements ara applicable from the O , point in time it' is-identified that a Limiting Condition for Operation is : not hn _  ! met'.' The time limit 5-of'the ACTION requirements are also applicable (wher a

, L"- system or. component is'- removed from service for -surveillance testinD .or d.

< , linvest iget too .of operational ~ problems. Individual specifications may include

a specified , time limit for the completion of a Surveillance Requirement when C_ M- f equipapent - is removed from cervien. In this case, the allowable outage time j

$%, ylimit'shof the' ACTION requirements are applicable when this limit expires if the 1 surveillance has not been completed. .When a shutdown is required to 1

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g, ,Leomply with ACTION requirements, the plant may have entered an OPERATIONAL h4

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-CONDITION. in which=a new specification becomes applicable. In this case, the

-timellimits of?the ACTION requirements would apply fro 11 the point in time that pg- "

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L ' Soect'ficat ion ' 3. 0. 3. establishes the shutdown ACTION requiremerits that 1must:

p% C ibef --implemented g wheni fa( Limiting; .Coridition>for-Operation is not met andf the Q.  : condition :is not specifically, addressed by the . associated ACTION; requirements.

y>- 1The' purpose of:this- specif(cation is. to delineate the r time limits- for placing; Q,i ,

?th G nit Din; a< safe shutdownL;CONDITIONEwaen plant; operation cannot? bej W# malesained )within..the: limitsJ-for safe operation' defined by'the Limiting

? ?Copditions(for;0peration;and=its ACTION requirements. :Ittis:not(-intended: to,

, N bedused> J as 4an = ; operational: convenience = which p?rmits Jroutine) voluntaryg Mt ~ [remo'valsoff redundant (systems- or compenents from Service -in lieu of_ other .

.' 1alternatises-ithat twould =not: result"in redundant systems or components ~being.

.W L 41noperableh 'Onet h our'is allowed to;preparesfor an orderly _ shutdown- before' s"' finitiating e .a tchangen Tin pl'ant . operation.1This time -permits the operator to M"< Jcoordinate:the reductioniin.electricaligerieration with.the, load dispatcher to'

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V c ' ensureithe stability rand availability of the electrical gridF - The ' time limits .

y 4 3specified:to lreachilower, . CONDITIONS = ;of operation ' permit thei shutdown to?

, o iproceed;iin J a~ controlled and orderly = manner that_is well within;the specified

]" ;J _ [ "maximuni cool'down rate and within the -cooldown capabilities of the ifacility-

< assuming onlyithe minimum _ required equipment is. OPERABLE.~This reduces thermal y_-  : stresses on components oflthe pr imary coolant system and ,the: potential. for a i

_ _ 4~ , i qplant apsetl that. :could; challenge safety systems under CONDITIONS for which RC T <

.st his ! speci fic. at ion. applies.

7,' .4 iIffremedial measures ' permitting limited continued operation of the facility under"the provisions of.the. ACTION requirements are. completeo, the: shutdown

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- requirements have ceen met or the time. limits of the ACT10N requirements. 'have f, "not ' expired,- thus: providing an allowance for the completion of the. required

, 1 Lactions.-

[ The time limits of Specificat ion. 3. 0. 3. allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in

. COLD SHUTDOWN when;a shutdowr. is required during POWER operatlon.

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If ' the l v '

l plant' is in a lower CONDITION of operation when a shutdown is required, the 1 4; 4 , ; < time' limit for , reaching : the next lower CONDITION of operation applies.

However,-'if- a lower CONDITION of operation is reached in less time th.

y allowed,~the totaltallowable: time to reach COLD SHUTDOWN, or other OpFRATIONAL

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I CONDITION, is not-reduced. For example, if STARTUP is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time a* wed to reach h0T SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to en2.. HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed thai; would permit a return to POWER operation,. a penalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL CONDITION or CONDITION of ll operation for another specification in which the requirements of the Limiting

, . Condition _ for Operation are not met. If the new specification becomes

. applicable in less time than specified, the difference may be added to the allowable outaDe- time limits of the second- specification. However, the allowable outage time limits of ACTION requirements for a higher CONDITICN of operation may not be used to extend the alloiable outage time that is applicable when a LimitinD Condition for Qeration is not met in a Icwer CONDITION of operation.

The shutdown requirements of specification 3.0.3. do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Sperification 3. 0. 4. establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher CONDITION of operation'when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being taken to obtain .;ompliance with a specification oy restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that pertait continord operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation

,[ without regard to the status of the plant before or after a change in f OPERATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL

, CONDITION or other specified CONDITION may be made in accordance with tha i provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsir.g the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

It- When a shutdowr is required to comply with ACTION requirements, the provisions I of specification 3. 0. 4. do not apply because they would delay placing the facility-in a lower CONDITION of operation, f

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Specificationn 4.0.1. throuch 4. 0. 5. establish the general requirements applicable to Surveillance Requirements. These requirements are based on the

' Surveillance Requi rement stated in the Code of Federal Regulations, 10 CFR

50. 36 (c) (3) :

" Surveillance requirements are requirements relatinD to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the Liciting Conditions of Operation will be met."

Soerification 4.0.1 establishes the requirement that surveillances must be performed during the OpEPATIONAL CONDITIONS or other CONDITIONS for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of.this specification is to ensure that surveillances are performed to verify the operational. status of systems and components and that param3ters are within specified limits to ensure safe operation of the facility when the plant is in an OpERATIJNAL CONDITION or other specified condition for which the individual Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for~which the requirements of the associated Limited Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requiremen+s of a specification.

Specification 4. 0. 2. establishes the conditiens under which the specified

' time interval for Surveillance Requirements may be extended. The specification permits an allcwable extension of the normal surveillance interval; to facilitate surveillance scheduling, and consideration of plant operating CONDITIONS, that may not be suitable foi conducting the surveillance; e.g., transient conditions or Aner ongoing surveillance or maintenance activities. The limit given in Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not J significantly degraded beyond that obtained from the specified surveillante interval. It is not intended that the allowable tolerance be used as a convenience to repeatedly schedule the performance of surveillances at the allowable tolerance limit.

h Scecification 4.0.3. establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this LASALLE - UNIT 2 B 2/4 0-5 PROPOSED AMENDMENT b

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                                                      ?pr*ltilon disjtoibeVconstruedj as5 = implying t that systems or components are
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$7>W J (OpEMBLEiwhenj they Lare found f or, :knownito be . inoperable although ' stills meet ing n          '
                 ~.           ,_                        ltheH Surveillance C Requirements. _ JThis y specification' also clarifles that the; in " A. ; ACTION;irequirements are applicable when: Surve111ancel Requirements;=have not?                                                                                                                          i k4N ' ao r
                              ' [ ! ; beenE completed f within: Lthe D allowed ; surveillance 'intervalt and that ' the time;
                                                     'flimits ofi the ~ ACTION o requirements '- apply' fromi the L point in; time - it- isl                                        .

fd* ,? " TidentifiedlthatTaisurveillance=has:not-been; performed'and'not,at~the-timethat-8W ' G the' Tallowed < surveillance Ginterval--:was: Jesceeded.c _l Completion Loff thei DSurWillance RequirementLwithin th'e allowable; outage' time -limits- off the. ACTION -

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i:6 A< _ - l requirements: restores compli'ance:with the iequirements of. Specification 4.0.3.s ggOf! 9 , 4, However/ =this does not; negate the: fact _that the failure to have; performed'the-FR4 # fsurveillance?withinLtheLallowed surveillance; interval, . defined: by? .the= $# M VJprovisions#offSpectfication-_4.3.2, Jwas1 a; violation- of- the--OPERABILITY: 1 R I ' 3requirementsiof(a; Umiting LCondition) .for_ Operation _<that- is _ subject f __ to - j7 g^Ti->; ' -ielnforcement; provisionsaction.L Further,:s of, Specification thelfailurei 14.0.2 to performaaTechnicalC Sis a violation-of surveillance witSin-the Specification E - _:crequirement'and lis,(therefore, a reportable evert. under the requirement's of 10j ML '

                                       ^ 7CFR 50i?3(a) (2)li) (B) : because 1t= is !a -_ condition : prohibited by the3 -plant's=

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IffthsM1owable outaDe_ time limits of the ACTION requirements are -less 'than ,

         *~                                           ; 24bhours1 orf aishu',down:is required sto comply with ACTION requirements, e.g.,

N "> g Specification?3.0.3., a 24-hourfallowance is provided to spermit 'a:Edelay7:in; p% 4 :hjimplementingitheACTION~ requirements. . This_'provides an: adequate -time _ limit: to- ' a rs ~ 1 Ecomplete Surveillance Requirements thatihave not been performed.1 JThez purpose .Qy ~ . dofQthiS[;l allowance; EisG to; permit -(the completion of?a surveillance ,before?a-D  % TshutdoWnfwouldibe! required to complyJwith ACTION-requirementstor beforeD other e a , 1: remedial;? measures would ybel_ required? thatsmay..preclud_e the completion.of;a: x

                             ,Qw , Msurveillance.1 .The basisiforithis allowance: includes consideration forf plant
   %                                    ,,            Iconditions, adequate planning,- availability of: personnel, > the time.: required-to-Vy5 _ _. < pet ormfthe                                                  f               ! surveillance,i 'andt(the safety signit t r.ance : of the -. delay tin:

pf J t' L11mit? completing;Et_he required surveillance.1 sThis provision also provides a.' time

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for, the complet ion 'of Surveillance Requirements that/ tbecome , applicable - g% MT* f as 'La 1 consequence = ofc OPERATIONAL' CONDIfl0N changes; imposed 1 by>~ ACTION' gy' C: 1"! [ requirements?and for' completing; Surveillance Requirements that fare applicable:

                                              . c : whenian eMeeption- to the requirements of sSpecification 4.0. 4 is allowed.i - 1,f' a ~

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                                             $       ? surveillance:is not completed within the' 24-hour allowance, - the _ time. limits of
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4 4M :A  % Lthe: ACTION _, requirements'areiapplicable at that time. When a surveillance is. p,;'? -

                                                        - performed -within: the 24-hour allowance and the Surveillance > Requirements are-A
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thatlthe surveillance is terminated. 3 w- a F Q t g 4' DSurveillance ~ Pequirements do not have to be performed on inoperable equipment - because:the ACTION requirements ' define. the remedial measures that apply.- b' " ' fHowever, L 't he' Surveillance Requirements have to be met to demonstrate that _ tinoperable equipment has been restored to OPERABLE status.

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he  ! Sneci fi cat ion- 4. O. 4 establishes the requirement that all applicable o

        .,                                       ."..surveillances must;be-met 1before' entry into an OPERATIONAL CONDITION or other                                                                                     9'
       *.       s                                       ' coridit ion : offoperation specified in the Applicability statement. The purpose A

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Miyj -idfl(thisispeAlficat_lon:is toi ensure that system and. component - : OPERABILITY -

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n requirements E orf parametem7. limits are met-before entry into_an OPERATIONAL

                                                            ;CONDITIONforfother specified condition for which these. systems and components-R ,' h~

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ensureLJ safelloperation of the facilit' y.y This' provision applies to changesTin:

fgg 7 ;0PERATIONAL; CONDITIONS o.r'other specified: CONDITIONS associated with , plant: '

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                                                                                                                                         .                                       :u K      1 qunder theF provisionsgof- this specificatlon, L the - applicable ,Surveillence
                                                          ?; requirements ^lmust) ;be. performed within the specified surveillance interval to -
 @                      W , iJ ensure lthatithe! Limiting ConditionsLfor. Operation are' met:during inittal plant ~
         'O- '_ startupior$following;afplantioutage.<

s _- [ -[Wh n a shutdowncis? required to comply _ with' ACTION requirements, the provisions- X

$-14 '                                                        off Specificationt.4.0.'4h do: not-(apply ^ because this would delay. placing lthe-                                             m
          ,                             ,y                   (facilityiin} allo'erwCONDITION yf operation.                     1 m                          ,                                   L ..                  . -.                 , _

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                                                     ' L Soecification' 4.0.5.~ establishes the~ requirement that inservice inspection of f                                                   ,

fW %ASME Code-Class;1,1 2 ,Jand>3 components and -inservice testing:'.of ASME Code? q San , Classpli 2,;'andE 3 pumps and valves shall'be performed in accordance with-a' ' - 9 1periodicallyf updated ' version of Section XI of the . ASME Boiler- andt-pressure. ' M@; " ' , SVessel1 Codel and:;Addendab asi required by110 CFR 50.55a. These requirements

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                                 ,                         ijapplyfexcept.: when relief has been provided' in writing' by the; Commission.
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                                                .         - Thi_sh speelfication includes a_ clarification of the frequencies for performing -

ithexinservice finspection .and= testing activities required by Section _X1 of ? :the - 7 _ . _ fASME['Boi.ler_Eand; < pressure , Vessel Code and applicablet Addenda.5 This fclarification;is>provided toJensure . consistency i_n surveillance ~-intervals. ( ;throughout1the TechnicallSpecifications and to remove any ambiguities relative " tofthe4 frequencies Efop ? performing .the: Lrequired? inservice c-inspection and du ', , ttesting activitles.1 p k.' 4 ,m

                                           "              [Under!thefterms :of this .specificatlon, the, more - restrictive requirements -of Lth'e: Technidal Specifications takeiprecedence over the'. ASME Boiler andlpressure M? '                               "~

j Vsssel? Code andl applicable Addenda.

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The requirements of Specification'.4.0.4; f (ton, perform'surveillanc.e activities before entry into an OPERATIONAL CONDITION-y ' for otherJspect fled condition _ takes precedence over the L ASME Boiler xand y .q , tpressure, Vessel 'LCode-provisions.that allows pumps and valves to be tested,up i 'to?!oneiweek'after return to normal ~ operation. The Technical specification k'g g (definition of OPERABLE does not allow a grace period'before a component,' which

                           -                    -         ils/notfeapable'of performing its specifled function,                                          is declared inoperable s                      4 3 - u (and: stakes precedence, oven the ASME Boiler and pressure vessel. code provision
                                                           ,th'atfallows a valve to be incapable of performing its specified function' for--

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                                                    ' 1 up tot 24_ hours before being. declared inoperable.

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