Text

Amends 94 & 78 to Licenses NPF-11 & NPF-18,respectively, Revising TS 3.0.4,4.0.3 & 4.0.4 to Incorporate Guidance Provided in GL 87-09
	ML20067D499
Person / Time
Site:	LaSalle
Issue date:	02/24/1994
From:	Dyer J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20067D502	List: ML20067D499; ML20067D523;
References
	GL-87-09, GL-87-9, NUDOCS 9403080252
	Download: ML20067D499 (105)
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5.3 MGy o

UNITED STATES 8')

/n NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20055

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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-11 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated December 15, 1989, as supplemented September 16, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorind by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-ll is hereby amended to read as follows:

9403080252 940224 PDR ADOCK 05000373 P

PDR

3 i

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

94, and the Environmental Protection Plan j

contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the l

Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective immediately to be implemented within 60 days j

from its date of issuance.

i FOR THE NUCLEAR REGULATORY COMMISSION

' u t.

ev l

ames E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation i

Attachment:

l Changes to the Technical l

Speci ficat ions Date of Issuance:

February 24, 1994 i

I l

l

ATTACHMENT TO LICENSE AMENDMENT NO. 94 FACILITY OPERATING LICENSE NO NPF-ll l

DOCKET NO. 50-373 l

l Replace the following pages of the Appendix "A" Technical Specifications with i

the enclosed pages.

The revised pages are identified by amendment number and contain a vertical line indicating the area of change.

Pages identified by an asterisk are provided for convenience.

REMOVE INSERT 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2 3/4 1-4 3/4 1-4 3/4 1-6 3/4 1-6 3/4 1-8 3/4 1-8 3/4 1-9 3/4 1-9 3/4 1-11 3/4 1-11 3/4 1-14 3/4 1-14 3/4 3-1 3/4 3-1 3/4 3-9 3/4 3-9 i

l 3/4 3-27 3/4 3-27 3/4 3-40 3/4 3-40

3/4 3-55

3/4 3-55 3/4 3-56 3/4 3-56 3/4 3-60 3/4 3-60 3/4 3-63 3/4 3-63 3/4 3-73 3/4 3-73 3/4 3-75 3/4 3-75 3/4 3-85 3/4 3-85 3/4 4-1 3/4 4-1 l

3/4 4-lb 3/4 4-10 3/4 4-10 l

3/4 4-21 3/4 4-21 3/4 4-22 3/4 4-22 l

3/4 6-22 3/4 6-22 3/4 7-9 3/4 7-9

3/4 7-10

3/4 7-10 l

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2-REMOVE (continued)

INSERT (continued) 3/4 7-11 3/4 7-11 3/4 7-14 3/4 7-14 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-22 3/4 7-22 3/4 7-33 3/4 7-33 3/4 8-22 3/4 8-22 3/4 8-26 3/4 8-26 3/4 8-27 3/4 8-27 3/4 8-28 3/4 8-28 3/4 8-29 3/4 8-29 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 B 3/4 0-1 B 3/4 0-1 8 3/4 0-2 B 3/4 0-2 B 3/4 0-3 B 3/4 0-3 B 3/4 0-4 B 3/4 0-4 l

B 3/4 0-5 l

B 3/4 0-6 l

B 3/4 0-7 i

B 3/4 0-8 l

l

g 1

I l

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 l

other conditions specified therein; except that upon failure to meet the I

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 in the associated ACTION requirements, within I 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' l.

At least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 4

l 3.

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

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 Specifications.

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

3.0.4 Entry into an OPERATIONAL CONDITION or other specified CONDITION shall not be made when the conditions for the Limiting Conditions for 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 through or to OPERATIONAL CONDITIONS as required 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 solely l

because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting l

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) and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.

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

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

l LA SALLE - UNIT 1 3/4 0-1 AMENDMENT NO. 94

APPLICABILITY l

SURVElllANCE RE0VIREMENTS 1

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

4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 l

percent of the specified surveillance interval.

l 4.0.3 Failure to perform a Surveillance Requirement within the allowed I

surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a 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, i

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the I

ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not l

have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable l

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 orevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

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 l

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

10 CFR 50, Section 50.55a(g) except where specific written relief hasbeengrantedbytheCommIssionpursuantto10CFR50,Section 50.55a(g)(6)(1),

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 i

l inspection and testina 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 I

LA SALLE - UNIT 1 3/4 0-2 AMENDMENT NO. 94

~

REACTIVITY CONTROL SYSTEM i

LIMITING CONDITION FOR OPERATION (Continued} _

ACTION (Continued) 2.

If the inoperable control rod (s) is inserted:

a)

Within,1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months disarm the associated directional control 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , d'.

With one or more SDV vent or drain lines with one valve inoperable, 1.

Isolate" the associated line within 7 days.

2.

Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , e".

With one or more SDV vent or drain lines with both valves inoperable, 1.

Isolate" the associated line within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

2.

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

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

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

b.

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

4.1.3.1.2 When above the low power setpoint of the RWM, all withdrawn control rods not required to 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 j

b.

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

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

"These valves may be closed intermittently for testing under administrative 4

control.

" Separate Action statement entry is allowed for each SDV vent and drain line.

"An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

LA SALLE - UNIT 1 3/4 1-4 Amendment No. 94

j REACTIVITY CONTROL SYSTEij CONTROL R0D MAXIMUM SCRAM INSERTION TIMES i

LIMITINGCONDIT;0NFOROPERATION 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 7.0 seconds.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

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

7.0 seconds

1.

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

l 2.

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

Otherwise, be in at least HOT SHUT 00WN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l SURVEILLANCE REQUIREMENTS l

4.1.3.2 The maximum scram insertion time of the control rods shall be l

demonstrated through measurement with reactor coolant pressure greater than or l

equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:

a.

For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or after a reactor shutdown 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 control rod movement.

LA SALLE - UNIT 1 3/4 1-6 Amendment No. 94

9 i

REACTIVITY CONTROL SYSTEM j

FOUR C041ROL 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 control rods in each group of four control rods arranged in a two-by-two array, based on deenergization of the scram pilot valve i

solenoids as time zero, shall not exceed any of the following:

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.

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 2.

Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with an 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l 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 j

4.1.3.2.

l l

LA SALLE - UNIT 1 3/4 1-8 Amendment No. 94

REACTIVITY CONTROL SYSTEM CONTROL R0D 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*.

ACTION:

a.

In OPERATIONAL CONDITION 1 or 2:

1.

With one control rod scram accumulator inoperable:

a)

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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 H0T SHUTDOWN within the next l

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2.

With more than one control rod scram accumulator inoperable, declare the associated control rod inoperable and:

l 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 withdrawn 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 l

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 5 with:

1.

One withdrawn control rod with its associated scram l

accumulator inoperable, insert the affected control rod and I

disarm the associated directional control valves within I hour, either:

a)

Electrically, or Hydraulically by closin b) water isolation valves.g the drive water and exhaust 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.

'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.

LA SALLE - UNIT 1 3/4 1 Amendment No. 94 l

3 1

1 REACTIVITY CONTROL SYSTEM f

CONTROL R0D ORIVE 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 CONDITIONS 1 and 2 with one control rod not coupled to its associated drive mechanism:

1.

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

a)

If permitted by the RWM, 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 then until permitted by the RWM, declare the control rod inoperable and insert the control roi and disarm the associated directional control valves either:

1)

Elactrically, 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

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

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. 94

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.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the position of each control rod is a.

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 That the control rod position indicator corresponds to the control c.

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.

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. 94

I 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING 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.

l ACTION:

a.

With the number of OPERABLE channels less than required by the Minimum l

OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channels and/or trip system in the tripped condition within I hour.

l b.

With the number of OPERABLE channels less than require 1 by the Minimum I

OPEPABLE Channels per Trip System requirement for bott trip systems, place at least one trip system in the tripped condition wit hin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE RE0VIREMENTS 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.

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

l l

4.3.1.3 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 l

limit at least once per 18 months.

Each test shall include at least one channel per trip system such that all channels are tested'at least once every N times I

18 months where N is the total number of redundant channels in a 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 OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

"If more channels are inoperabie in one trip system than in the other, select that trip system to place in the tripped condition, except when this would i

cause the Trip Function to accur.

LA SALLE - UNIT 1 3/4 3-1 Amendment No. 94 l

J

INSTRUMENTATION f

3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentattor, channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown l

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 Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or trip system in the tripped con-dition within one hour.

l c.

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

i

'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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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. 94

+

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 OPERABLE Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within one hour or declare the l

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 inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ADS trip system or ECCS inoperable.

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.

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or l

declare the associated ADS trip system or ECCS inoperable.

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

For one trip system, place that trip system in the tripped condition within one hour or declare the HPCS system l

inoperable.

b.

For both trip systems, declare the HPCS system inoperable.

I ACTION 36 - Deleted i

ACTION 37 - With the number of OPERABLE instruments less than the Minimum l

Operable Instruments, place the inoperable instrument (s) in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or declare the associated j

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

l LA SALLE - UNIT 1 3/4 3-27 Amendment No. 94

INSTRUMENTATION END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1.

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Limiting Condition for Operation (LCO) to the E0C-RPT inoperable value per Specification 3.2.3 within the next I hour or, 2.

reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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.

4.3.4.2.3 The END-0F-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 its limit at least once per 18 months.

Each test shall include at least the logic of one type of channel it.put, turbine control valve fast closure or turbine stop valve closure, such Got both types of channel inputs are tested at least once per 36 months. The tine allotted for breaker arc suppression shall be verified by test at least once per 60 months.

LA SALLE - UNIT 1 3/4 3-40 Amendment No. 94

TABLE 4.3.6-1 (Continued)

CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:

a.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup, if not performed within the previous 7 days.

c.

Includes reactor manual control multiplexing system input.

With THERMAL POWER 1 30% of RATED THERMAL POWER.

With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

f

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)

i v

i

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x./

LA SALLE - UNIT 1 3/4 3-55 M

c.:w.

i 1

INSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 Specification 3.0.3 are not applicable, 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 CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1.

i i

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

LA SALLE - UNIT 1 3/4 3-56 Amendment No. 94

a INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3

2

,, seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall 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 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 Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 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 TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1.

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 OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 and submitted to the Commission pursuant to Specification 6.6.C within 10 days describing the magnitude, fre-quency spectrum and resultant effect upon unit features important to safety.

l l

"The Seismic 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.

LA SALLE - UNIT 1 3/4 3-60 Amendment No. 94

O INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.7.3-1 shall be OPERABLE.,onitoring instrumentation channels shown in Table 3.3.7.3 The meteorological m 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 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 instrumentation to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL i

CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

l

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 OPERATIONAL CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 3-63 Amendment No. 94

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

)

b.

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

l 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:

l a.

With one or more TIP measurement locations inoperable, required measurements 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 l

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 data obtained from a 3-dimensional BWR core simulator code normalized with available operating measurements, provided the total number of simulated channels (measurement locations) does not exceed:

i a)

All channels of a single TIP machine, or l

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.

l c.

The provisions of Specification 3.0.3 are not applicable.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use for the above applicable monitoring or calibration functions, i

I l

0nly the detector (s) in the required measurement location (s) are required to be OPERABLE.

LA SALLE - UNIT 1 3/4 3-73 AMENDMENT NO. 94

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

I b.

Restore the minimum number of instraments to OPERABLE status within 14 days or, prepare and submit a Special Report to the Commission 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 Specification 3.0.3 are not applicable.

SURVEILLANCE 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 by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

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 instru-ments shall be demonstrated OPERABLE at least once per 6 months.

Supervised circuits with detectors which are inassessible during unit operation shall be l

demonstrated OPERABLE during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

The 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. 94 I

l

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.

{

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVElllANCE REQUIREMENTS l

4.3.7.12 Each channel of the loose-part detection system shall be demonstrated OPERABLE by performance of:

i l

a.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , i

l b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and j

c.

CHANNEL CALIBRATION at least once per 18 months.

l l

[

i l

LA SALLE - UNIT 1 3/4 3-85 Amendment No. 94 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM 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 control system in the Master Manual mode or lower, and b)

Increase the 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.

Otherwise, be in at least HOT SHUTDOWN within the next twelve (12) hours, b.

With no reactor coolant recirculation loops in operation:

1.

Take the ACTION required by Specification 3.4.1.5, and i

2.

Be in at least H0T SHUTOOWN within the next six (6) hours.

l LA SALLE - UNIT 1 3/4 4-1 Amendment No. 94

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION l

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval and, for conductivity and chloride concentration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months 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.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval or, for conductivity and chloride concentration, for more than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.

With the conductivity exceeding 10 pmho/cm at 25'C or chloride concentration exceeding 0.5 ppm, be in at least H0T SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN as rapidly as the cooldown rate limit permits.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , c.

At all other times:

1.

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

2.

With the chloride concentration exceeding the limit specified in i

Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , perform an engineering l

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 Amendment No. 94

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:

1.

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

a)

Restore the inoperable valve (s) to OPERABLE status, or b)

Isolate the affected main steam line by use of a deactivated MSIV in the closed position.

2.

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

SURVEILLANCE REQUIREMENTS 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.

LA SALLE - UNIT 1 3/4 4-21 Amendment No. 94

REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY 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 1 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.

c.

With the structural integrity of any ASME Code Class 3 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 componcat(s) from service.

SURVEILLANCE RE0VIREMENTS 4.4.8 No additional Surveillance Requirements other than those required by Specification 4.0.5.

LA SALLE - UNIT 1 3/4 4-22 Amendment No. 94

I j

CONTAINMENT SYSTEMS l

3/4.6.3 PRIMARY (_0NTAINMENT 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.

j LCTION:

I With one or more of the primary containment isolation valves shown a.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 flange.*

l 2.

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

I b.

With one or more of the reactor instrumentation line excess flow l

check valves shown in Table 3.6.3-1 inoperable:

1.

Operation may continue and the provisions of Specification 3.0.3 are not applicable provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

lsolation valves closed to satisfy these requirements may be reopened on an l

intermittent basis under administrative control.

LA SALLE - UNIT 1 3/4 6-22 Amendment No. 94 I

i o

PLANT SYSTEMS 3/4.7.4 SEALED SOURCE CONTAMINATION LjMITINGCONDITIONFOROPERATION 3.7.4 Each sealed source containing radioactive material cither in excess of i

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:

1 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, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.4.1 Test Reauirements - 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 Freauencies - Each category of sealed sources, excluding startup 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 Amendment No. 94

i PLANT SYSTEMS l

SURVEILLANCE REQUIREMENTS (Continued) i b.

Stored sources not in use - Each sealed source and fission detector i

shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

d j

Startup sources and fission detectors - Each sealed startup source a

c.

and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4 4.7.4.3 Reports - A report shall be prepared and submitted to the Commission j

on an annual basis if sealed source or fission detector leakage tests reveal i

the presence of greater than or equal to 0.005 microcuries of removable contamination.

i i

O 4

4 9

LA SALLE - UNIT 1 3/4 7-10

PLANT SYSTEMS 3/4.7.5 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 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 gpm, with their discharge aligned to the fire 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 l

of the deluge valve on each deluge or spray system required to be l

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 l

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 alternate backup pump or supply.

The provisions of Specification 3.0.3 are not applicable.

l b.

With the fire suppression water system otherwise inoperable:

1.

Establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

Prepare and submit a Special Report in accordance with Specification 6.6.C; a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b)

Confirmed by telegraph, mailgram or facsimile 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, i

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

LA SALLE - UNIT 1 3/4 7-11 Amendment No. 94

PLANT SYSTEMS j

1 DELVGE AND/0R 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 required 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 next 30 days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

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 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.

l 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:

I 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 CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 1 3/4 7-14 Amendment No. 94 l

. b

PLANT SYSTEMS CO SYSTEMS 2

LIMITING CONDITION FOR OPERATION systems of Unit 1 and Unit 2 shall be 3.7.5.3 The following low pressure CO2 OPERABLE.

a.

Division 1 diesel generator 0 room, b.

Division 2 diesel generator lA room.

c.

Division 3 diesel generator IB room, d.

Unit 2 Division 2 diesel generator 2A room.

APPLICABILITY: Whenever equipment protected by the low pressure C02 systems is required to be OPERABLE.

ACTION:

a.

With one or more of the above required low pressure CO systems 2

inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 Com-mission 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, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.5.3 Each of the above required low pressure CO systems shall be 2

demonstrated OPERABLE:

a.

At least once per 7 days by verifying CO storage tank level to be 2

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 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 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. 94

PLANT SYSTEMji FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.5.4 The fire hose stations of Unit 1 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, routo an additional fire hose of equal or greater diameter to the unprotected area (s)/ zone (s) from an OPERABLE hose station within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the inoperable fire hose station (s) to 0PERABLE status within 14 days or, prepare and submit a Special Report 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.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVElllANCE REQUIREMENTS 4.7.5.4 Each of the above required fire hose stations shown in Table 3.7.5.4-1 shall be demonstrated OPERABLE:

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:

1.

Visual inspection of the fire hose stations not accessible j

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 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.

LA SALLE - UNIT 1 3/4 7-18 Amendment No. 94

.._._ _ _._ _ ~

PLANT SYSTEMS 3/4.7.6 FIRE RATED ASSEMBLIES llMITING 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 fire area, and all sealing devices in fire rated assembly penetrations (fire 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 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 pursuant to Specification 6.6.C within the next 30 days outlining the action taken, the cause of the inoperable i

l fire rated assembly (s) and/or sealing device (s) and plans and l

schedule for restoring the fire rated assembly (s) and/or. sealing device (s) to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

SURVElllANCE 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 and associated hardware.

l c.

At least 10 percent of each type of sealed penetration.

If apparent changes in appearance or abnormal degradations are found, a visual t

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. 94 I

L

l

~

1 PLANT SYSTEMS 3/4.7.10 MAIN TURBINE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION l

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.

j ACTION:

With the main turbine bypass system inoperable:

1.

If at least four bypass valves are capable of accepting steam j

flow per Surveillance 4.7.10.a:

4 a)

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 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.

b)

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

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months increase the MCPR LC0 to the main turbine bypass inoperable value per Specification 3.2.3, and b)

Within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months restore the system to OPERABLE status.

c)

Otherwise, reduce THERMAL POWER to less than 25% of RATED i

THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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.

94 1

l ELECTRICAL POWER SM_TJ,MM PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES

}

4 LIMITING CONDITION FOR OPERATION 3.8.3.2 Primary and backup primary containment penetration conductor overcurrent protective devices associated with each primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt) electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration qn rating.

APPLICABILIT). JPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one or more of the primary containment penetration conductor overcurrent protective devices inop'

'a, restore the protective device (s) to OPERABLE status or de-e.wrgize t

uit(s) by tripping the associated circuit breaker or racking out o.

..: moving the inoperable circuit breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable, and verify the circuit breaker to be tripped or the inoperable circuit breaker racked out, or remcved, at least once per 7 days thereafter.

Otherwise, be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE0VIREMENTS 4.8.3.2 Each of the p ary containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1.

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

a)

A CHANNEL CAllBRATION of the associated protective relays, and b)

An integrated system functional test of the breakers 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, i

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.

LA SALLE - UNIT 1 3/4 8-22 Amendment No. 94

i

[LECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION l

3.8.3.3 The thermal overload protection of each valve shown in s

l Table 3.8.3.3-1 shall be bypassed continuously or under accident conditions, I

as applicable, by an OPERABLE bypass device integral with the motor starter.

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

ACTION:

With the thermal overload protection for one or more of the above required l

valves not bypassed continuously or under accident conditions, as applicable, by an OPERABLE integral bypass device, take administrative action to continuously bypass the thermal overload within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).

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 l

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.

LA SALLE - UNIT 1 3/4 8-26 Amendment No. 94 l

a.

r ELECTRICAL POWER SYSTEMS i

TABLE 3.8.3.3-1 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE SYSTEM (S)

VALVE NUMBER (Continuous)(Accident Conditions)

AFFECTED a.

IVG001 Accident Conditions SBGTS IVG003 Accident Conditions 2VG001 Accident Conditions 2VG003 Accident Conditions b.

IVP113A Accident Conditions Primary containment IVPll3B Accident Conditions chilled water coolers IVPil4A Accident Conditions IVPll48 Accident Conditions IVP053A Accident Conditions IVP053B Accident Conditions IVP063A Accident Conditions IVP063B Accident Conditions c.

IVQO38 Accident Conditions Primary containment IVQO32 Accident Conditions vent and purge system IVQO35 Accident Conditions IVQ047 Accident Conditions IVQ048 Accident Conditions IVQ050 Accident Conditions l

IVQ051 Accident Conditions IVQ068 Accident Conditions l

IVQ037 Accident Conditions d.

1WR179 Accident Conditions RBCCW system l

LWR 180 Accident Conditions IWR040 Accident Conditions LWR 029 Accident Conditions e.

1821 - F067A Accident Conditions Main steam system i

1821 - F067B Accident Conditions 1B21 - F067C Accident Conditions 1821 - F0670 Accident Conditions 1821 - F019 Accident Conditions 1821 - F016 Accident Conditions l

l LA SALLE - UNIT 1 3/4 8-27 Amendment No. 94 l

i

TABLE 3.8.3.3-1 (Continued) l MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/0R BYPASS DEVICES BYPASS DEVICE SYSTEM (S)

VALVE NUMBER (Continuous)(Accident Conditions)

AFFECTED e.

1821 - F020 Continuous Main steam system IB21 - F068 Continuous 1821 - F070 Continuous 1821 - F069 Continuous 1821 - F071 Continuous 1821 - F072 Continuous 1821 - F073 Continuous f.

1821 - F065A Continuous Main feedwater system 1821 - F065B Continuous 9

IE21 - F001 Continuous LPCS system lE21 - F005 Accident Conditions lE21 - F011 Accident Conditions IE21 - F012 Accident Conditions h.

IC41 - F001A Accident Conditions SBLCS 1C41 - F001B Accident Conditions i.

IG33 - F001 Accident Conditions RWCU 1G33 - F004 Accident Conditions j.

lE12 - F052A Accident Conditions RHR system lE12 - F064A Accident Conditions 1E12 - F087A Accident Conditions lE12 - F004A Continuous lE12 - F047A Continuous 1E12 - F048A Accident Conditions 1E12 - F003A Continuous lE12 - F026A Accident Conditions lE12 - F068A Continuous lE12 - F073A Continuous lE12 - F074A Continuous 1E12 - F011A Accident Conditions lE12 - F024A Accident Conditions lE12 - F016A Accident Conditions lE12 - F017A Accident Conditions IE12 - F027A Accident Conditions lE12 - F004B Continuous IE12 - F047B Continuous 1E12 - F048B Accident Conditions l

1E12 - F0038 Continuous 1E12 - F068B Continuous lE12 - F073B Continuous lE12 - F074B Continuous 1E12 - F026B Accident Conditions lE12 - F0llB Accident Conditions LA SALLE - UNIT 1 3/4 8-28 Amendment No. 94

TABLE 3.8.3.3-1 (Continued) l MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/0R BYPASS DEVICES BYPASS DEVICE SYSTEM (S)

VALVE NUMBER (Continuous)(Accident Conditions)

AFFECTED j.

1E12 - F024B Accident Conditions.

RHR system l

IE12 - F006B Continuous IE12 - F016B Accident Conditions 1E12 - F017B Accident Conditions IE12 - F042B Accident Conditions IE12 - F064B Accident Conditions IE12 - F093 Continuous lE12 - F021 Accident Conditions l

1E12 - F004C Continuous IE12 - F052B Accident Conditions lE12 - F087B Accident Conditions lE12 - F099B Accident Conditions lE12 - F099A Accident Conditions lE12 - F008 Accident Conditions lE12 - F009 Accident Conditions lE12 - F040A Accident Conditions lE12 - F040B Accident Conditions IE12 - F049A Accident Conditions lE12 - F049B Accident Conditions lE12 - F053A Accident Conditions IE12 - F053B Accident Conditions lE12 - F006A Continuous i

lE12 - F023 Accident Conditions lE12 - F027B Accident Conditions IE12 - F042A Accident Conditions l

lE12 - F042C Accident Conditions i

1E12 - F064C Accident Conditions 1E12 - F094 Continuous k.

lE51 - F086 Accident Conditions RCIC system lE51 - F022 Accident Conditions 1E51 - F068 Continuuus l

1E51 - F069 Continuous lE51 - F080 Accident Conditions lE51 - F046 Accident Conditions lE51 - F059 Accident Conditions IE51 - F063 Accident Conditions IE51 - F019 Accident Conditions lE51 - F031 Continuous lE51 - F045 Accident Conditions i

1E51 - F008 Accident Conditions l

lE51 - F010 Accident Conditions IE51 - F013 Accident Conditions IE51 - F064 Accident Conditions IE51 - F076 Accident Conditions i

LA SALLE - UNIT 1 3/4 8-29 Amendment No. 94 l

l

3/4.11 RADI0 ACTIVE EFFLVENTS 3/4.11.1 LIOUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 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 ODCM.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1 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.

LA SALLE - UNIT 1 3/4 11-1 Amendment No. 94

RADI0 ACTIVE EFFLUENTS 3/4 11.2 GASE0US EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.2.1 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.

LA SALLE - UNIT 1 3/4 11-2 Amendment No. 94

i 3/4.0 APPLICABIllTY BASES Specifications 3.0.1 throuah 3.0.4 establish the general requirements applicable to the Limiting Conditions for Operation.

These requirements 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 l

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."

Specification 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 (routine) 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 facility 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

-1 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 from the point in time it is identified that a Limiting Condition for Operation-is not met.

The time limits of the ACTION requirements ~ are also applicable when a i

i system or component is removed from. service for surveillance testing or investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed.

When a shutdown is required to LA SALLE - UNIT 1 B 3/4 0-1 Amendment No. 94 I

4 3/4.0 APPLICABILITY BASES 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 the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Specification 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 specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification, and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition for 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 condition is not specifically addressed by the associated ACTION requirements.

l The purpose of this specification is to delineate the time limits for placing l

the unit in a safe shutdown CONDITION when plant operation can not be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements.

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 l

thermal stresses on components of the primary coolant system and the potential l

for a 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 may be 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 not expired, thus providing an allowance for the completion of the required actions.

LA SALLE - UNIT 1 B 3/4 0-2 Amendment No. 94 l

l

---re--+

r l

l 3/4.0 APPLICABILITY l

BASES l

The time limits of Specification 3.0.3. allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in i

COLD SHUTDOWN when a shutdown is required during POWER operation.

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

However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced.

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

Therefore, if remedial measures 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 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 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 outage time limits of ACTION requirements for a hir;her CONDITION of operation may not be used to extend the allowable outage t1me 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 taken.

l Specification 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 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 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 LA SALLE - UNIT I B 3/4 0-3 Amendment No. 94

3/4.0 APPLICABILITY BASES 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.

Specification 3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements 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 inoperable solely because of the inoperability of its normal or emergency power source.

The provisions of Specification 3.0.5 are not applicable to the HPCS system, electrical division 3 or diesel generator IB.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months out-of-service time when emergency diesel generator 0 or lA is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source, diesel generator 0 or lA, 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 emergency 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, Specification 3.8.1.1 requires in part that two physically independent circuits between the offsite transmission network and LA SALLE - UNIT 1 B 3/4 0-4 Amendment No. 94

O

3/4.0 APPLICABILITY BASES the onsite Class 1E distribution system be OPERABLE.

The ACTION statement provides a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months out-of-service time when both required offsite circuits are j

not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 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 statements for each of the applicable LCOs.

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 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 (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.

Specifications 4.0.1 throuah 4.0.5 establish the general requirements applicable to Surveillance Requirements.

These requirements are based on the Surveillance Requirement stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

" Surveillance requirements are requirements relating to test, calibration, or inspection to assure 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 requirement that surveillances must be performed during the OPERATIONAL 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 parameters are within 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 Limiting Conditiont 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 Limiting Condition for Operation LA SALLE - UNIT 1 B 3/4 0-5 Amendment No. 94

3/4.0 APPLICABillTY BASES do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special 2

Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended.

The specification permits an allowable extension of the normal surveillance interval; to facilitate surveillance scheduling, and consideration of plant operating CONDITIONS, that may not be suitable for conducting the surveillance, e.g.,

i transient conditions or other 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 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.

I Specification 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.

l 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 provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time 4

limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

i However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the 4

provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the plant's 1

Technical Specifications.

LA SALLE - UNIT 1 B 3/4 0-6 Amendment No. 94

3/4.0 APPLICABillTY BASES If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time 4

limit for the completion of Surveillance Requirements that become applicable as a consequence of OPERATIONAL CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of i

the ACTION requirements are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status, i

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that 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.

l Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant i

startup or following a plant outage.

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

LA SALLE - UNIT 1 B 3/4 0-7 Amendment No. 94

3/4.0 APPLICABillTY BASES Specification 4.0.5 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 Addanda as required by 10 CFR 50.55a. These requirements 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 testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals 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 Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDri10N or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provisions that allows pumps and valves to be tested up to one week after return to normal operation.

The technical specifica. tion definition sf OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

l l

\\

?

LA SALLE - UNIT 1 B 3/4 0-8 Amendment No. 94 1

ff o

UNITED STATES

g y

g NUCLEAR REGULATORY COMMISSION f.

'j WASHINGTON, D. C. 20555 I

'+,

1 l

COMMONWEALTH EDISON COMPANY DOCKET N0. 50-374 LASALLE COUNTY STATION. UNIT 2

{

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. NPF-18 i

1.

The Nuclear Regulatory Commission (the Commissien) has found that:

i A.

The application for m:.ndment filed by the Commonwealth Edison i

Company (the licensee), dated December 15, 1989, as supplemented j

September 16, 1992, complies with the standards and requirements j

of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; i

B.

The facility will operate in conformity with the application, the j

provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorized i

by this amendment can be conducted without endangering the health and safety of the public, and (ii).that such activities will be i

conducted in compliance with the Commission's regulations set l

forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; j

and 5

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

l 2.

Accordingly, the license is amended by changes to the Technical i

Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is i

hereby amended to read as follows:

I 4

4 4

I i

4

-..v,,-

.,,n-,

sn.,~

v--

e

,~,

' (2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No 78, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective immediately to be implemented within 60 days from its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f.

ev James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 24, 1994 l

l l

l t

l l

ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. NPF-18 l

DOCKET NO. 50-374 I

Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and l

contain a vertical line indicating the area of change.

Pages identified by an l

asterisk are provided for convenience.

REMOVE INSERT 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2 3/4 1-4 3/4 1-4 3/4 1-6 3/4 1-6 t

3/4 1-8 3/4 1-8 3/4 1-9 3/4 1-9 3/4 1-11 3/4 1-11 3/4 1-14 3/4 1-14 3/4 3-1 3/4 3-1 3/4 3-9 3/4 3-9 3/4 3-27 3/4 3-27 3/4 3-39 3/4 3-39 3/4 3-57 3/4 3-57

3/4 3-58

3/4 3-58 l

3/4 3-60 3/4 3-60 3/4 3-63 3/4 3-63 3/4 3-73 3/4 3-73 3/4 3-75 3/4 3-75 3/4 3-85 3/4 3-85 l

3/4 4-1 3/4 4-1 3/4 4-2a 3/4 4-11 3/4 4-11

3/4 4-12

3/4 4-12

3/4 4-21

3/4 4-21 3/4 4-22 3/4 4-22 3/4 4-23 3/4 4-23

3/4 4-24

3/4 4-24 3/4 6-25 3/4 6-25 3/4 7-9 3/4 7-9

3/4 7-10

3/4 7-10 i

l l

,~

--,, ~ -..,

,n.

p-,,,--,

l l

- REMOVE (continued)

INSERT (continued) 3/4 7-11 3/4 7-11 3/4 7-14 3/4 7-14 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 3/4 7-23 3/4 7-23 3/4 7-34 3/4 7-34 3/4 8-22 3/4 8-22 3/4 8-26 3/4 8-26 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 B 3/4 0-1 B 3/4 0-1 B 3/4 0-2 B 3/4 0-2 B 3/4 0-3 B 3/4 0-3 B 3/4 0-4 B 3/4 0-4 B 3/4 0-5 B 3/4 0-6 B 3/4 0-7 B 3/4 0-8 l

,m

.m

3/4.0 APPLICABillTY LIMITINGCONDITION[,QROPERATION succeedingSpecificationsisrequiredduringtheOPEberationcontainedinthe 3.0.1 Compliance with the Limiting Conditions for 0 TIONAL 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 in the associated ACTION requirements, within I 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.

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

l 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 Specifications. ptions to these requirements are stated in the individual Operation.

Exce l

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

l l

3.0.4 Entry into an OPERATIONAL CONDITION or other specified CONDITION shall not be made when the conditions for the Limiting Conditions for 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 through or to OPERATIONAL CONDITIONS as required 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 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),

satisfy the requirements of this s(pecification.(s) are OPERABLE, or likewise subsystem (s), train (s), component s) and device l

Unless both conditions 1) and (2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.

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

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

LA SALLE - UNIT 2 3/4 0-1 Amendment No. 78

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

1 4.0.2 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

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 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be performed on inoperable equipment.

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 OPERATIONAL CONDITIONS as required to comply with ACTION requiroments.

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 hasbeengrantedbytheCommIssionpursuantto10CFR50,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:

l ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing insoection and-testina 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 l

1 i

LA SALLE - UNIT 2 3/4 0-2 Amendment No. 78

~. _

REACTIVITY CONTROL SYSTEM LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) 2.

If the inoperable control rod (s) is inserted:

a)

Within,1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months disarm the associated directional control 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l c.

With more than 8 control-rods, inoperable, be in at least HOT SHUTDOWN within 12. hours.

d'.

With one or more 50V vent or drain lines with one valve inoperable, 1.

Isolate" the associated line within 7 days.

2.

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

e".

With one or more SDV vent or drain lines with both valves inoperable, 1.

Isolate" the associated line within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

2.

Otherwise, be in H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVElllANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

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

b.

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

I 4.1.3.1.2 When above the low power setpoint of the RWM, all withdrawn control rods not required to have their directional control valves disarmed i

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is immovable as a result of excessive friction or mechanical interference.

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

- These valves may be closed intermittently for testing under administrative control.

" Separate Action statement entry is allowed for each SDV vent and drain line.

l "An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

.LA SALLE - UNIT 2 3/4 1-4 Amendment No. 78

REACTIVITY CONTROL SYSTEM CONTROL R00 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-energization of the scram 1

pilot valve solenoids as time zero, shall not exceed 7.0 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

i ACTION:

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

7.0 seconds

1.

Declare the control rod (s) with the slow insertion time inoperable, and 2.

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

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

SURVElllANCE REQUIREMENTS 4.1. 3. 2 The maximum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:

a.

For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or after a reactor shutdown 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 control rod movement.

LA SALLE - UNIT 2 3/4 1-6 Amendment No. 78

j e

i i

BEACTIVITY CONTROL SYSTEM l

FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES l

LIMITING CONDITION FOR OPERATION l

3.1.3.4 The average scram insertion time, from the fully withdrawn position, for j

the three fastest control rods in each group of four control rods arranged in a j

two-by-two array, based on deenergization of the scram pilot valve solenoids as

]

time zero, shall not exceed any of the following:

Position Inserted From Average Scram Inser-Fully Withdrawn tion Time (Seconds) 45 0.45 39 0.92 25 2.05 i

05 3.70 i

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With the average scram insertion times of control rods exceeding the 2

above limits:

1.

Declare the cot trol rods with the slower than average scram insertion times inoperable until en analysis is performed to determine that required scram reactivity remains for the slow faur control rod group, and i

2.

Perform the Surveillance Requ;rcments of Specification 4.1.3.2.c at least i

once per 60 days when operation is continued with an average scram insertion time (s) in excess of the average scram insertion time limit.

i i

Otherwise, be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

I 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.

l i

LA SALLE - UNIT 2 3/4 1-8 Amendment No. 78

REACTIVITY CONTROL SYSTEM CONTROL R00 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*.

ACTION:

a.

In OPERATIONAL CONDITION 1 or 2:

1.

With one control rod scram accumulator inoperable:

a)

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 withdrawn 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 closin water isolation valves.g the drive water and exhaust Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , either:

l 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 I

operating, immediately place the reactor mode switch in the 1

l Shutdown position.

)

i 1

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 2 3/4 1-9 Amendment No. 78

REACTIVITY CONTROL SYSTEM CONTROL R00 DRIVE C0VPLING 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 CONDITIONS 1 and 2 with one control rod not coupled to its associated drive mechanism:

1.

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

a)

If permitted by the RWM, 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.

l b)

If recoupling is not accomplished on the first attempt or, if not permitted by the RWM then until permitted by the RWM, 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l b.

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

l b)

Hydraulically by closing the drive water and exhaust water j

isolation valves.

At least each withdrawn control rod. Not applicable to control rods removed per t

l 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 2 3/4 1-11 Amendment No. 78

o 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.

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

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 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.

'At least each withdrawn control rod not applicable to control rods removed per Speci fications 3.9.10.1 or 3.9.10.2.

LA SALLE - UNIT 2 3/4 1-14 Amendment No. 78

~

3/4,3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.1 As a minimum, the reactor protection system instrumentation channels

.i 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.

ACTION:

i a.

With the number of OPERABLE channels less than required by the Minimum 4

OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channels and/or trip system in the tripped condition

within I hour.

b.

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 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 CHELK, 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 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 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 j

channel per trip system 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 j

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 OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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. 78 i

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 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 Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or trip system in the tripped condition

within one hour.

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 *** within one hour and take the ACTION required by Tabl e 3.3.2-1.

An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.

In these cases, the inoper-able channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION 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 whare this would cause the Trip Function to occur.

In these cases, the inoper-able channel shall be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

LA SALLE - UNIT 2 3/4 3-9 Amendment No. 78

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 OPERABLE Channels per Trip Function requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within one hour or declare the j

associated system inoperable.

1 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 0PERABLE 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 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ADS trip system or ECCS inoperable.

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.

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the associated ADS trip system or ECCS inoperable.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement a.

For one trip system, place that trip system in the tripped condition within one hour or declare the HPCS system inoperable.

b.

For both trip systems, declare the HPCS system inoperable.

ACTION 36 -

Deleted ACTION 37 -

With the number of OPERABLE instruments less than the Minimum Operable Instruments, place the inoperable instrument (s) in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.

LA SALLE - UNIT 2 3/4 3-27 Amendment No. 78 l

INSTRUMENTATION JND-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION l

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 i

setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.2-2 and with the END-0F-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:

I 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 Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 inopereble channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within I hour.

2.

If the inoperable channels include two turbine control valve 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , otherwise, either:

1.

Increase the MINIMUM CRITICAL POWER (MCPR) Limiting Condition for Operation (LCO) to the E0C-RPT inoperable value per Speci-fication 3.2.3 within the next I hour, or 2.

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

With both trip systems inoperable, restore at least one trip system e.

to OPERABLE status within I hour, 1.

Increase the MINIMUM CRITICAL POWER (MCPR) Limiting Condition for Operation (LCO) to the E0C-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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

LA SALLE - UNIT 2 3/4 3-39 Amendment No. 78

INSTRUMENTATION

~

3/4.3.7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 Specification 3.0.3 are not applicable.

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 CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1.

i i

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

LA SALLE - UNIT 2 3/4 3-57 Amendment No. 78

..m._

~.

4 e

TABLE 3.3.7.1-1 x

y RADIATION MONITORING INSTRUMENTATION F

rn MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT g

INSTRUMENTATION OPERABLE CONDITIONS SETPOINT RANGE ACTION

a. Main Control Room 2/ intake 1,2,3,5 and

3.5 mR/hr-0.1 to 10,000 mR/hr 70 m

Atmospheric Control System Radiation Monitoring Subsystem i

TABLE NOTATIONS wg

When irradiated fuel is being handled in the secondary containment.

T E

ACTION STATEMENT I

ACTION 70 -

i a.

With one of the required monitors inoperable, place the inoperable channel in the downscale tripped condition within I hour; restore the inoperable channel to OPERABLE status within 7 days, or, within the next 6_ hours, initiate and maintain operation of the control room emergency filtration system in the pressurization mode of operation.

b.

With both of the required monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the pressurization mods of operation within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

o-INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall ba OPERABLE.**

APPLICABILITY: At all timet.

ACTION:

a.

With one or more seismic monitoring instruments 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 instrument (s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 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 TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-I.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.02g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 and submitted to the Commission pursuant to Specification 6.6.C within 10 days describing the magnitude, fre-quency spectrum and resultant effect upon unit features important to safety.

The Seismic 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.

LA SALLE - UNIT 2 3/4 3-60 Amendment No. 78

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATIONo 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 tcan 7 days, prepare and submit a Special Report to the Commission purstant to specification 6.6.C rithin the next 10 days outlining the ct"se of the malfunction and the plans for restoring the instrumentet.icn to OPERABLE status.

b.

The provisions 'of Specification 3.0.3 are not applicable.

SURVEILLANCE 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.

2

The Mataorological 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.

LA SALLE - UNIT 2 3/4 3-63 Amendment No. 78 l

i w.

~ _,.,

.,.m-,

.--.,,-v_-.

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 i

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.

1 2.

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

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.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by i

normalizing each of the above required detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use for the above applicable monitoring or calibration functions.

l

0nly the detector (s) in the required measurement location (s) are required to be OPERABLE.

LA SALLE - UNIT 2 3/4 3-73 Amendment No. 78

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detecticr. 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 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the con-tainment 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 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 Specification 3.0.3 are not applicable.

SURVEILLANCE 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 by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

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 instru-ments shall be demonstrated OPERABLE at least once per 6 months.

Supervised circuits with detectors which are inassessible during unit operation shall be demonstrated OPERABLE during each COLD SH JT00WN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

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

LA SALLE - UNIT 2 3/4 3-75 Amendment No. 78

? e2 INSTRUMENTATf0N 1

l LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.12 The loose-part detection system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS I and 2.

i ACTION:

l 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.

l b.

The provisions of Specification 3.0.3 are not applicable.

I SURVEILLANCE RE0VIREMENTS 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at least once per 18 months.

l l

LA SALLE - UNIT 2 3/4 3-85 Amendment No. 78

3/4.4 REACTOR COOLANT SYSTEM i

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

APPLICABILITY: OPERATIONAL CONDITIONS I 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 control system in the Master Manual mode or lower, and i

l b)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety l

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, l

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.

Otherwise, be in at least H0T SHUTDOWN within the next twelve (12) hours, b.

With no reactor coolant recirculation loops in operation:

1.

Take the ACTION required by Specification 3.4.1.5, and 2.

Be in at least H0T SHUTDOWN within the next six (6) hours.

l LA SALLE - UNIT 2 3/4 4-1 Amendment No. 78 l

l l

l

REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY 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.

1 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval and, for conductivity and chloride concentration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, but with the conductivity less than 10 pmho/cm at 25'C and with the chloride 4

concentration less than 0.5 ppm, this need not be reported to the Commission.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval or, for conductivity and chloride concentration, for more than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3.

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

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

c.

At all other times:

1.

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

2.

With the chloride concentration exceeding the limit specified in Table 3.4.4-1 for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 2 3/4 4-11 Amendment No. 78

~ REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.4 The reactor coolant shall be determined to be within the specified chemistry limit by:

a.

Measurement prior to pressurizing the reactor during each startup, if not performed within the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b.

Analyzing a_ sample of the reactor coolant:

1.

Chlorides at least once per:

a) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever conductivity is greater than 1.0 pmho/cm at 25*C.

2.

Conductivity at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

3.

pH at least once per:

a) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever conductivity is greater than 1.0 pmho/cm at 25 C.

c.

Continuously recording the conductivity of the reactor coolant, or, when the continuous recording conductivity monitor is inoperable for up to 31 days, obtaining a dip or flow through conductivity measurement at least once per:

4 1.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months in OPERATIONAL CONDITIONS 1, 2 and 3, and 2.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at all other times.

d.

Performance of a CHANNEL CHECK of the continuous conductivity monitor with a flow cell at least once per:

1.

7 days, and 2.

_24 hours whenever conductivity is greater than 1.0 pmho/cm at 25*C.

LA SALLE - UNIT 2 3/4 4-12

I REACTOR COOLANT SYSTEM i

REACTOR STEAM DOME LIMITING CONDITION FOR OPERATION-3.4.6.2 The pressure in the reactor steam dome shall be less than 1020 psig.

APPLICABILITY:

OPERATIONAL' CONDITIONS 1* and 2*.

ACTION:

With the reactor steam dome pressure exceeding 1020 psig, reduce the pressure to less than 1020 psig within 15 minutes or be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.6.2 The reactor steam dome pressure shall be verified to be less than 1020 psig at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l l

l

Not applicable during anticipated transients.

I l

l LA SALLE - UNIT 2 3/4 4-21 l

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REACTOR COOLANT SYSTEM l

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:

1.

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

a)

Restore the inoperable valve (s) to OPERABLE status, or l

l b)

Isolate the affected main steam line by use of a deactivated MSIV in l

the closed position.

2.

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

SURVEILLANCE RE0VIREMENTS 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.

LA SALLE - UNIT 2 3/4 4-22 Amendment No. 78

4 -

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REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY 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:

i a.

With the structural integrity of any ASME Code Class 1 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 l

Coolant System temperature more than 50*F above the minimum temperature required by NOT 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 l

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

With the structural integrity of any ASME Code Class 3 component (s) c.

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) from service.

SURVEILLANCE REQUIREMENTS 4.4.8 No additional Surveillance Requirements other than those required by Specification 4.0.5.

l l

LA SALLE - UNIT 2 3/4 4-23 Amendment No. 78

REACTOR COOLANT SYSTEM 3/4.4.9 RESIDUAL HEAT REMOVAL HOT SHUT 00WN LIMITING CONDITION FOR OPERATION 3.4.9.1 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and at least one shutdown cooling mode loop-shall be in operation * ## with each loop consisting of at least:

i a.

One OPERABLE RHR pump, and b.

One OPERABLE RHR heat exchanger.

APPLICAB!i.ITY:

OPERATIONAL CONDITION 3, with reactor vessel' pressure less l

than the Rh'Tcut-in permissive setpoint.

j

. ACTION:

a.

With less than the above required RHR shutdown cooling mode loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible.

Within t

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

Be in at least COLD SHUTOOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .**

b.

With no RHR shutdown cooling mode loop in. operation, immediately initiate corrective action to return at least one loop to operation as soon as possible.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish reactor coolant'circula-l tion by an alternate method and monitor reactor coolant temperature l

and pressure at least once per hour, l

SURVEILLANCE REQUIREMENTS i

l 4.4.9.1 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

0ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other loop is OPERABLE and in operation.

The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months j

per 8-hour period provided the other loop is OPERABLE.

1

1. The RHR shutdown cooling mode loop may be removed from operation during hydrostatic testing.

- Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

LA SALLE - UNIT 2 3/4 4-24

.l 1

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.

APPLICABillTY: 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 flange.*

l l

2.

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

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

l b.

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

1.

Operation may continue and the provisions of Specification l

3.0.3 are not applicable provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

L a)

The inoperable valve is returned to OPERABLE status, or i

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

LA SALLE - UNIT 2 3/4 6-25 Amendment No. 78

PLANT SYSTEMS 3/4.7.4 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.4 Each sealed source containing radioactive material ei+her 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 l

Regul ations.

b.

The provisions of Specification 3.0.3 are not applicable.

SVRVElllANCE RE0VIREMENTS l

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

a.

The licensee, or 1

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 Freauencies - Each category of sealed sources, excluding startup 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:

1.

With a ha'f-life greater than 30 days, excluding Hydrogen 3, and 2.

In any form other than gas.

LA SALLE - UNIT 2 3/4 7-9 Amendment No. 78

(

o.-

0 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Sealed sources transferred.

without a certificate indicating the last test date shall be tested prior to being placed into use, c.

Startuo sources and fission detectors - Each !.ealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.4.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable l

contamination.

l l

l I

l LA SALLE - UNIT 2 3/4 7-10 i

.Y e

PLANT SYSTEMS 3/4.7.5 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 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 gpm, with their discharge aligned to the fire 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 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 alternate backup pump or supply.

The provisions of Specification 3.0.3 are 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and 2.

Prapare and submit a Special Report in accordance with Specification 6.6.C; a)

By telephone within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b)

Confirmed by telegraph, mailgram or facsimile 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 l

plans and schedule for restoring the system to OPERABLE status.

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

LA SALLE - UNIT 2 3/4 7-11 Amendment No. 78 I

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

APPLICABILITY: Whenever equipment protected by the deluge / sprinkler systems are required 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 next 30 days outlining the action taken, the cause of the inoper-ability and the plans and schedule for restoring the system to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable, SURVEILLANCE REQUIREMENTS l

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 l

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 CONDITION 4 or 5 or when defueled.

l LA SALLE - UNIT 2 3/4 7-14 Amendment No. 78

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-_w-PLANT SYSTEMS C0 SYSTEMS 2

LIMITING CONDITION FOR OPERATION 3.7.5.3 The following low pressure CO systems of Unit I and Unit 2 shall be 2

OPERABLE.*

a.

Division 1 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.

APPLICABILITY: Whenever equipment protected by the low pressure CO systems 2

is required to be OPERABLE.

ACTION:

a.

With one or more of the above required low pressure C0 systems 2

inoperable, within I hour establish a continuous fire watch with backup fire'suporession 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 Com-mission 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, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.7.5.3 Each of the above required low. pressure CO systems shall be 2

demonstrated OPERABLE:

a.

At least once per 7 days by verifying CO, 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 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 or emergency power source may be inoperable in OPERATIONAL CONDITION 4 or 5 or when defueled.

LA SALLE - UNIT 2 3/4 7-17 Amendment No. 78

[

i PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION 3.7.5.4 The fire hose stations of Unit 1 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 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Restore the inoperable fire hose station (s) to OPERABLE status within 14 days or, prepare and submit a Special Report 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.

l b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS I

4.7.5.4 Each of the above required fire hose stations shown in Table 3.7.5.4-1 shall be demonstrated OPERABLE:

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:

1 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 g'iskets and replacing any degraded gaskets in l

the couplings.

c.

At least once per 3," ears 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.

LA SALLE - UNIT 2 3/4 7-18 Amendment No. 78

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j PLANT SYSTEMS 1

l 3/4.7.6 FIRE RATED' ASSEMBLIES j

LIMITING CONDITION FOR OPERATION 1

i 3.7.6 All fire rated assemblies, including walls, floor / ceilings, cable tray 1,

enclosures and other fire barriers separating safety-related fire areas or separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable and piping penetration seals and i

ventilation seals) shall be OPERABLE.

i

,i APPLICABILITY: At all times.

j ACTION:

i j

a.

With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within I hour either establish a con-i tinuous fire watch on at least one side of the affected assembly (s) j and/or device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and/or sealing 3

device (s) and establish an hourly fire watch patrol.

Restore the i

inoperable fire rated assembly (s) and/or sealing device (s) to OPERABLE status within 7. days or, prepare and submit a Special j

Report to the Commission pursuant to Specification 6.6.C within the 4

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 j

device (s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

3 SURVEILLANCE RE0VIREMENTS l

4.7.6.1 Each of the above required fire rated assemblies and sealing devices i

shall be verified to be OPERABLE at least once per 18 months by performing a visual inspection of:

4 a.

The exposed surfaces of each fire rated assemblies.

j b.

Each fire window / fire damper and associated hardware.

3 c.

At least 10 percent of each type of sealed penetration.

If apparent j

changes in appearance or abnormal degradations are found, a visual inspection of an additional 10 percent of each type of sealed 4

penetration shall be made.

This inspection process shall continue until a 10 percent sample with no apparent changes in appearance or j

abnormal degradation is found.

)

LA SALLE - UNIT 2 3/4 7-23 Amendment No. 78 er,

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i PLANT SYSTEMS 1

j 3/4.7.10 MAIN TURBINE BYPASS SYSTEM l

LIMITING CONDITION FOR OPERATION j

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.

j ACTION:

I With the main turbine bypass system inoperable:

1 j

1.

If at least four bypass valves are capable of accepting steam j

flow per Surveillance 4.7.10.a:

l a)

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

1) Restore the system to OPERABLE status, or 1

2)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) a l

Limiting Condition for Operation (LCO) to the main turbine bypass inoperable value per Specification 3.2.3.

i b)

Otherwise, reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , i

2.

If less than four bypass valves are capable of accepting steam j

flow per Surveillance 4.7.10.a:

i a)

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months increase the MCPR LC0 to the main turbine i

bypass inoperable value per Specification 3.2.3, and i

l b)

Within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months restore the system to OPERABLE status.

c)

Otherwise, reduce THERMAL POWER to less than 25% of RATED i

THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

LURVEILLANCEREQUIREMENTS i

4.7.10 The main turbine bypass system shall be demonstrated OPERABLE at least l

once per:

t a.

7 days by cycling each turbine bypass valve through at least one

{

complete cycle of full travel.

b.

18 months by:

1.

Performing a system functional test which includes simulated 4

i automatic actuation and verifying that each automatic valve J,

actuates to its correct position.

2.

Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less j

than or equal to 200 milliseconds

]

LA SALLE - UNIT 2 3/4 7-34 Amendment No. 78 f

I

ELECTRICAL POWER SYSTEMS PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.2 Primary and backup primary containment penetration conductor overcurrent protective devices associated with each primary containment medium and high voltage (6.9 kV, 4.16 kV and 480 volt) electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating.

i APPLICABillTY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one or more of the primary containment penetration conductor overcurrent protective devices inoperable, restore the 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , 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.

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

l SURVElllANCE REQUIREMENTS l

l 4.8.3.2 Each of the primary containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1.

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

a)

A CHANNEL CAllBRATION of the associated protective relays, and 1

b)

An integrated system functional test of the breakers overcurrent protective trip circuit which includes simulated automatic actuation of the trip system to l

demonstrate that the overall penetration protection design l

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 l

have been functionally tested.

LA SALLE - UNIT 2 3/4 8-22 Amendment No. 78 l

ELECTRICAL POWER SYSTEMS MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION LIMITING CONDITION FOR OPERATION 3.8.3.3 The thermal overload protection of each valve shown in Table 3.8.3.3-1 shall be bypassed continuously or under accHent conditions, l

as applicable, by an OPERABLE bypass device integral with the motor starter.

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

ACTION:

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 continuously bypass the thermal overload within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the affected valve (s) inoperable and apply the appropriate ACTION statement (s) for the affected system (s).

SURVEILLANCE RE0VIREME_NTS 4.8.3.3.1 The thermal overload protection for the above required valves shall be verified to be bypassed continuously or under accioent 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 bypassec 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.

LA SALLE - UNIT 2 3/4 8-26 Amendment No. 78

f 4

t 3/4.11 RADI0 ACTIVE EFFLVENTS I

3/4.11.1 LIOUID EFFLUENTS 1

LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION i

f 3.11.1.1 The quantity of radioactive material contained in any outside i

temporary tanks shall be limited to less than or equal to the limits calculated j

in the ODCM.

i 4

k APPLICABIllTY: At all times.

j ACTION:

1 a.

With the quantity of radioactive material in any of the above listed I

tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank j

contents to within the limit.

l b.

The provisions of Specification 3,0.3 are not applicable.

i l

l I

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SURVEILLANCE REQUIREMENTS i

4.11.1.1 The quantity of radioactive material contained in each of the above 2

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 j

radioactive materials are being added to the tank.

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LA SALLE - UNIT 2 3/4 11-1 Amendment No. 78 i

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s RADI0 ACTIVE EFFLUENTS 3/4 11.2 GASE0US EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

The provisions of Specification 3.0.3 are not' applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1 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.

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LA SALLE - UNIT 2 3/4 11-2 Amendment No. 78 l

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4 3/4.0 APPLICABILITY BASES Specifications 3.0.1 throuah 3.0.4 establish the general requirements applicable to the Limiting Conditions for Operation. These requirements 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 i

facility. When a Limiting Condition for Operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any l

remedial action permitted by the technical specification until the condition can be met."

Specification 3.0.1 establishes the Applicability statement, located within each individual specification, as the requirement for when (i.e., in which l

OPERATIONAL CONDITIONS or other specified CONDITIONS) conformance to the l

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-(routine) 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.

l There are two basic types of ACTION requirements.

The first specifies the remedial measures that permit continued operation of the facility 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 l

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 l

l in an OPERATIONAL CONDITION or other specified CONDITION in which the l

specification no longer applies.

l l

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit exoires if the surveillance has not been completed.

When a shutdown is requi-to LA SALLE - UNIT 2 B 3/4 0-1 Amendment No. 78 I

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J 3/4.0 APPLICABILITY BASES l

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 j

the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Specification 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 specification is to clarify that (I) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition for 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 condition is not specifically addressed by the associated ACTION requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown CONDITION when plant operation can not be mair,tained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements.

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 1

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 stresses on components of the primary coolant system and the potential for a 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 ArTION requirements are completed, the shutdown may be 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 not expired, thus providing an allowance for the completion of the required actions.

LA SALLE - UNIT 2 B 3/4 0-2 Amendment No. 78

3/4.0 APPLICABILITY BASES The time limits of Specification 3.0.3. allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation.

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

However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach H0T SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time l

to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

l Therefore, if remedial measures 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 than the total time allowed.

l 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 i

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 outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable 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 taken.

Specification 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 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 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 LA SALLE - UNIT 2 8 3/4 0-3 Amendment No. 78

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6 3/4.0 ApPLICABIllTY BASES 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.

Specification 3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements 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, componerts 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 inoperable solely because of the inoperability of its normal or emergency power source.

The provisions of Specification 3.0.5 are not applicable tc the HPCS system, electrical division 3 or diesel generator 18.

For 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months out-of-service time when emergency diesel generator 0 or 2A is not OPERABLE.

If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source, diesel generator 0 or 2A, 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 emergency diesel generator instead, provided the other specified conditions are satisfied.

In this case, this would mean that the l

l 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 further example, Saecification 3.8.1.1 requires in part that'two physically independent circuits aetween the offsite transmission network and the onsite

r. lass 1E distribution system be OPERABLE.

The ACTION statement provides a 24 LA SALLE - UNIT 2 B 3/4 0-4 Amendment No, 78 i

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3/4.0 APPLICABILITY BASES hour out-of-service time when both required offsite circuits are not OPERABLE.

If the definition of OPERABLE were applied without consideration of l

Specification 3.0.5, all systems, subsystems, trains, components and devices I

supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable.

This would dictate invoking the applicable ACTION statements for each of the applicable LCOs.

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 normal power sources instead, provided the other specified conditions are satisfied.

In this case, l

this would mean that for one division the emergency power source must be OPERABLE (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.

i Specifications 4.0.1 throuah 4.0.5 establish the general requirements applicable to Surveillance Requirements.

These requirements are based on the Surveillance Requirement stated in the Code of Federal Regulations,10 CFR 50.36(c)(3):

" Surveillance requirements are requirements relating to test, calibration, or inspection to assure 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 requirement that surveillances must be performed during the OPERATIONAL 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 parameters are within 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 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 Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements o

associated with a Special Test Exception are only applicable when the Special LA SALLE - UNIT 2 8 3/4 0-5 Amendment No. 78

s 3/4.0 APPLICABILITY BASES Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0 2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended.

The specification i

permits an allowable extension of the normal surveillance interval; to facilitate surveillance scheduling, and consideration of plant operating CONDITIONS, that may not be suitable for conducting the surveillance, e.g.,

transient conditions or other 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 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.

Specification 4.0_3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the i

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 provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not i

been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

LA SALLE - UNIT 2 B 3/4 0-6 Amendment No. 78

3/4.0 APPLICABILITY BASES Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a j

surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of OPERATIONAL CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that 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 Limiting 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 of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.

Specification 4.0.5 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 LA SALLE - UNIT 2 B 3/4 0-7 Amendment No. 78

3/4.0 APPLICABILITY BASES 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 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 testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals 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 Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and 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 and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

1 LA SALLE - UNIT 2 B 3/4 0-8 Amendment No. 78

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