ML19332E235

Amend 53 to License NPF-18,revising Tech Specs by Deleting Specs Added Via Amend 30,to Allow Installation & Use of Fine Motion CRD (Fmcrd) During Cycle 2.Test for Which Fmcrd Installed Completed During Refueling Outage

ML19332E235
Person / Time
Site:	LaSalle  (NPF-18-A-053, NPF-18-A-53)
Issue date:	11/28/1989
From:	Jocelyn Craig Office of Nuclear Reactor Regulation
To:
Shared Package
ML19332E236	List: ML19332E235 ML19332E239
References
NUDOCS 8912060403
Download: ML19332E235 (16)

Text

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. UNITED STATES 3,-

NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D. C. 20656 l

COMMONWEALTH EDISUN COMPANY DOCKET h0. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. NPF-18

1. -

The Nuclear Regulatory Comission (the Comission or the NRC) has found' that:

A.

The application for amendment filed by the Comonwealth Edison Company (thelicensee),datedSeptember7,1988,May25,1989, and August 29, 1989 complies with the standards and req)uirements of the Atomic i

Energy. Act of 1954, as amended (the Act, and the Comission's L

regulations set forth in 10 CFR Chapter I; L

B.

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

provisions of the Act, and the regulations of the Comission; h

C.

There is reasonable assurance: (1)thattheactivitiesauthorizedby l1 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 h

the Comission's regulations and all applicable requirements have been l-satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan L

The Technical Specifications contained in Appendix A, as revised through l

Amendment No. 53

, 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.

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This amendment is effective upon date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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IJohn W.-Craig, Project Di tor

. Project Directorate III -,

s Division of Reactor Projects - III, IV, V and Special' Projects

Enclosure:

Changes to the Technical Specifications Date of' Issuance:' November 28, 1989 L

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ENCLOSURE.T0. LICENSE AMENDMENT. NO. 5.3 FACILITY.0PERATING LICENSE.NO..NPF-18 DOCKET NO. 50-374 Replace the following anges of the Appendix "A" Technical Specifications with the enclosed pages. Tie revised pages are identified by amendment nunber and contain a vertical line indicating the area of change.

REMOVE INSERT XI XI XVI XVI 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 i

3/4.1 3/4 1-6 l

l 3/4 1-7 3/4 1-7 3/41-8

~3/4 1-8 3/4 1-9 3/4 1-9 3/4 1-11 3/4 1-11 3/4.1-13 3/4 1-13 3/4 1-16 3/4 1-16 3/4 1-17 3/4 1-17 3/4 9-1 3/4 9-1 3/4 10-9 3/4 10 3/4 10 B3/4 10-2 v

v-

3 (e

j v

l d

yo sINDEX-l a.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

.i 1

1 1

i l}

'SECTION PAGE d

i i

i 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1. LIQUID. EFFLUENTS o

Concentration................................................

3/4 11-1 L

K Dose.........................................................

3/4.11-6 Liquid Waste Treatment. System................................

3/4 11-7 L i q u i d H ol d up T a n ks..........................................

3 /4 11-8 l

. 3/4 11.2. GASEOUS EFFLUENTS 4

Dose Rate....................................................

3/4 11-9 Dose-Noble Gases.............................................

3/4 11-13 Dose-Radioiodines,_ Radioactive Material in Particulate Form, and Radionuclides Other than Noble Gases.............

?/4 11-14 f

Gaseous Waste Treatment System...............................

3/4 11-15 L

L Ventilation Exhaust Treatment System.'........................

3/4 11-16 1

Explosive Gas Mixture........................................

3/4 11 Main Condenser...............................................- 3/4 11-18 Venting or Purging...........................................

3/4 11-19 i,

L 3/4 11.3 SOLID'RADI0 ACTIVE WASTE......................................

3/4 11-20 3/4 11.4 TOTAL D0SE...................................................

3/4 11 K 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING u

3/4 12.1 MONITORING PR0 GRAM...........................................

3/4-12-1 3/4 12.2 LAND USE CENSUS..............................................

3/4 12-9

- 3/4 12.3 INTERLABORATORY COMPARIS0N PR0 GRAM...........................

3/4 12-10 l

LA SALLE - UNIT 2 XI Amendment No. 53 1.

P p

INDEX

. BASES t

SECTION PAGE i

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 : PRIMARY CONTAINMENT INTEGRITY...........................

B 3/4 10-1

'3/4.10.2 R0D SEQUENCE CONTROL SYSTEM.............................

B 3/4 10-1 3/4.10.3' SHUTDOWN MARGIN DEMONSTRATIONS..........................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS.....................................

B 3/4 10-1 l

i 3/4.10.5 OXYGEN CONCENTRATION....................................

B 3/4 10 q 3/4.10.6 TRAINING STARTUPS.......................................

B 3/4 10-1 3/4.10.7 CONFIRMATORY FLOW INDUCED VIBRATION TEST................

B 3/4 10-1 5

I

- 3/4.11~ RADI0 ACTIVE EFFLUENTS l

3/4.11.1 LIQUID EFFLUENTS Concentration...........................................

B 3/4 11-1 Dose....................................................

B 3/4 11-1.

'l Liquid Waste Treatment System...........................

B 3/4 11-2 I

-Liquid Holdup Tanks.....................................

B 3/4 11-2 3/4.11.2 GASE0US EFFLUENTS

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Dose Rate...............................................

B 3/4'11-2 Dose - Noble Gases......................................

B 3/4 11-3 Dose -Radioiodines, Radioactive Materials in Particulate Form and Radionuclides Other than Noble Gases...........................................

B 3/4 11-3 1

L Gaseous Radwaste Treatment System and Ventilation L

Exhaust Treatment System..............................

B 3/4 11-4 l

Explosive Gas Mixture...................................

B 3/4 11-4 I

i L

Main Condenser..........................................

B 3/4 11-5 Venting or Purging......................................

B 3/4 11-5 3/4.11.3 SOLID RADI0 ACTIVE WASTE.................................

B 3/4 11-5 l

3/4.11.4 TOTAL D0SE..............................................

B 3/4 11-5 3/4.12 RADI0 ACTIVE ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM......................................

3/4 12-1 3/4 12.2 LAND USE CENSUS........................................

3/4 12-1 3/4 12.3 INTERLABORATORY COMPARIS0N PR0 GRAM......................

3/4 12-1 LA SALLE - UNIT 2 XVI Amendment No. 53

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3/4.1' REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.1.1 The SHUTDOWN MARGIN shall be equal to or greater than:

a.

0.38% delta k/k with the highest worth rod analytically determined, _

or b.

0.28% delta k/k with the highest worth rod determined by test.

APPLICABILITY:

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

l ACTION:

With the SHUTDOWN MARGIN less than specified:

a.'

In OPERATIONAL CONDITION 1 or 2, reestablish the required SHUTDOWN MARGIN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

In OPERATIONAL CONDITION 3 or 4, immediately verify all insertable L

control rods to be inserted and suspend all activities that

-could reduce the SHUTDOWN MARGIN.

In OPERATIONAL CONDITION 4, establish SECONDARY CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c.

In OPERATIONAL CONDITION.5, suspend CORE ALTERATIONS

• and other activities that could reduce the SHUT 00WN MARGIN, and insert all insertable control rods within I hour.

Establish SECONDARY L

CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.1' The SHUTDOWN MARGIN shall'be determined to be equal to or greater l

than specified at any time during the fuel cycle:

a.

By measurement, prior to or during the first startup after each refueling.

b. -

By measurement, within 500 MWD /T prior to the core average exposure at which the predicted SHUTDOWN MARGIN, including uncertainties and calculation biases, is equal to the specified limit, c.

Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after detection of a withdrawn control rod that is immovable, as a result of excessive friction or mechanical inter-o ference, or is untrippable, except that the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod.

• Except movement of IRMs, SRMs or special movable detectors.

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

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REACTIVITY CONTROL SYSTEM 3/4.1.3 CONTROL ROD 5 CONTROL R0D OPERABILITY LIMITING CONDITION FOR OPERATION 3.1.3.1 All control rods shall be OPERABLE.

I APPLICABILITY: OPERATIONAL CONDITIONS 1, and 2.

l ACTION i

a.

With one control rod inoperable due to being immovable, as a result of i

excessive friction or mechanical interference, or known to be untrippable:

1.

Within I hour:

a)

Verify that the inoperable control rod, if withdrawn, is separated from all other inoperable control rods by at l

E least two control cells in all directions.

b)

Disarm the associated directional control. valves

• either:

l 1)

Electrically, or 2)

Hydraulically by closing the drive water and exhaust water l

isolation valves.

l c)

Comply with Surveillance Requirement 4.1.1.c.

2.

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

3.

_ Restore the inoperable control rod to OPERABLE status within l

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l b.

With one or more control rods trippable but inoperable for causes other than addressed in ACTION a, above:

1 i

1.

If the inoperable control rod (s) is withdrawn:

i a)

Immediately verify:

1)

That the inoperable withdrawn control rod (s) is separated from all other inoperable withdrawn control rod (s) by at least two control cells in all directions, l_

and 2)

The insertion capability of the inoperable withdrawn l

control rod (s) by inserting the control rod (s) at least one notch by drive water pressure within the normal l

operating range **.

b)

Otherwise, insert the inoperable withdrawn control rod (s) and l

disarm the associated directional control valves

• either:

(

1)

Electrically, or 2)

Hydraulically by closing the drive water and exhaust water isolation valves 1.

"May be rearmed intermittently, under administrative control, to permit testing l

associated with restoring the control rod to OPERABLE status.

i.

• • The inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.

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

53 l

%,4 EACTIVITY CONTROL SYSTEM J #

CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION-FOR OPERATION s

L 3.1.3.2 The maximum' scram insertion time of each control rod from the fully withdrawn position to notch ~ position 05, based on de-energization of the scram o

pilot valve solenoids as time zero, shall not exceed 7 seconds.

' APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

l

-ACTION:

a.

With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

1.

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

Perform the Surveillance Requirements of Specification 4.1.3.2c.

at least once per 60 days when operation is continued v"h three or more control rods with maximum scram insertion times m excess of 7 seconds.-

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

The provisions of Specification 3.0.4 are not applicable, j

SURVEILLANCE REQUIREMENTS

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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:

L i

a.

For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIGNS* or after a reactor shutdown that is greater than 120 days, p

b.-

For specifically affected individual control rods following l

-maintenance on or modification to the cont.rol 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.

l "Except movement of SRM, IRM or special movable detectors or normal control rod movement.

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

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. REACTIVITY CONTROL SYSTEM

. CONTROL ROD AVERAGE SCRAM INSERTION TIMES

~ LIMITING CONDITION FOR OPERATION 3.1.3.3 The average scram insertion time of all OPERABLE control rods from the fully withdrawn position, based on de-energization.of the scram pilot valve solenoids as time-zero, shall not exceed any of the following:

Position Inserted From Average Scram Inser-i

Fully Withdrawn tion Time (Seconds) 45 0.43-39 0.86 i

25 1.93 05 3.49

. APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

l ACTION:

L

. With the average scram insertion time exceeding any of the above limits, be.in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.3 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.

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.LA SALLE - UNIT 2 3/4 1-7 Amendment No. 53

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REACTIVITY CONTR L SYSTEM t

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FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES

~ LIMITING CONDITION FOR OPERATION 3.1.3.4' The average scram insertion time, from the fully withdrawn position, for the three fastest control rods in each group of four control rods arranged in a.two-by-two array, based on deenergization'of the scram pilot valve solenoids as time zero, shall not exceed any of the following:

Position Inserted From Average Scram Inser-Fully Withdrawn tion Time (Seconds) 45 0.45 L

39 0.92 L

25 2.05 05 3.70 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

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ACTION:

a'.

With the average scram insertion times of control rods exceeding the above limits:

)

1 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 1

four control rod group, and 2.

Perform the Surveillance Requirements of Specification 4.1.3.2c.

L 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1 b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l.

4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.

I 53

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

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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*

l

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ACTION:

a.

In OPERATIONAL CONDITION 1 or 2:

1.-

With one control rod scram accumulator inoperable:

a)

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

1)

Restore the inoperable accumulator to OPERABLE status, or 2)

Declare the control rod associated with the inoperable accumulator inoperable.

b)

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

2.

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

a)

If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one CRD pump is operating by inserting at least one with-

' drawn control rod at least one notch by drive water pressure within the normal operating range or. place the i

reactor mode switch in the Shutdown position.

b)

Insert the inoperable control rods and disarm the associated directional control valves either:

1)

Electrically, or 2)

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

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

b.

In OPERATIONAL CONDITION 5 with:

l 1.

One withdrawn control rod with its associated scram accumulator l

inoperable, insert the affected control rod and disarm the l

associated directional control valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either:

L a)

Electrically, or b)

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

2.

More than one withdrawn control rod with the associated scrtm accumulator inoperable or with no control rod drive pump operating, immediately place the reactor mode switch in the Shutdown position.

c.

The provisions of Specification 3.0.4 are not applicable.

"At least the accumulator associated with each withdrawn control rod.

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

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

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. REACTIVITY CONTROL' SYSTEM CONTROL ROD DRIVE COUPLING'

't LIMITING' CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to th'eir drive mechanisms.

l

-APPLICABILITY: ~0PERATIONAL CONDITIONS 1, 2,'and 5*.

l c

ACTION:

l a.

In OPERATIONAL CONDITIONS I and 2 with one control rod not coupled to L

its associated drive mechanism:

1.-

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

i a)

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

1)

Observing any indicated response of the nuclear instrumentation,.and 2)

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

b)

If recoup 11ng is not accomplished on the'first' attempt or, if not permitted by the RWM or RSCS then until permitted by the RWM and RSCS, declare the control-rod inoperable and insert:the' control rod and disarm the associated directional control valves ** either:

1)

Electrically, or 2)

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

l 2.

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

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

1.

Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the' control rod and demonstrating that the control rod will not go to the overtravel position, or 2.

If recoupling is not accomplished, insert the control rod and disarm the' associated directional control valves ** either:

a)

Electrically, or b)

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

c.

The provisions of Specification 3.0.4 are not applicable.

"At least each withdrawn control rod.

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

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

d

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

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REACTIVITY CONTROL SYSTEM CONTROL ROD POSITION INDICA *i10N*

i LIMITING CONDITION FOR OPERATION 311.3.7 The control rod position indkation system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 5*.

l f

ACTION:

a.

In OPERATIONAL CONDITION 1 or 2 with ou. or more control rod position

[

indicators inoperable within one hour:

a,y 1.

Determine the position of the control rod by, (a) Moving the control rod, by single notch movement, to a position with an OPERABLE position indicator.

(b) Returning the control rod, by single notch movement, to its original position, and l

(c) Verifying no control rod drift alarm at least once per 12 l

hours, or 2.

lbve the control rod to a position with an OPERABLE position V

indicator, or 3.

When THERMAL POWER is:

i (a) Within the low power setpoint of the RSCS:

(1) Declare the control rod inoperable, I

(2) Verify the position and bypassing of control rod with inoperable " Full in" and/or " Full out" position indi-cators by a second licensed operator or other techni-cally qualified member of the unit technical staff.

b)

Greater than the low power setpoint of the RSCS, declare the control rod inoperable, insert tt.e control rod and c'isarm the associated directiond control valves ** either:

(1) Electrically, or (2) Hydraulically by closing the drive water and exhsust water isolation valves.

4.

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

"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 C*ERABLE status.

I LA SALLE - UNIT 2 3/4 1-13 Amendnent No. 53

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

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2*, when THERMAL POWER is less l

than or equal to 20% of RATED THERMAL POWER, the minimum allowable low power setpoint.

ACTION:

a.

With the RWM inoperable, verify control rod movement and compliance with the prescribed control rod pattern by a second licensed operator or other technically qualified member of the unit technical staff who is present at the reactor control console.

Otherwise, control rod movement may be only by actuating the manual scram or placing the reactor mode switch in the Shutdown position, b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANC,.EQUIREMENTS

}

4.1.4.1 The RWM shall be demonstrated OPERABLE:

a.

In OPERATIONAL CONDITION 2 prior to withdrawal of control rods for the purpose of making the reactor critical, and in OPERATIONAL CONDITION 1 prior to reaching 20% of RATED THERMAL POWER when reducing THERMAL POWER, by verifying proper annunciation of the selection error of at l ost one out-of-sequence control rod, b.

In OPERATIONAL CONDITION 2 prior to withdrawal of control rods for the purpose of making the reactor c-itical, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod.

c.

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

L d.

By verifying the control rod patterns and sequence input to the RWM computer is correctly loaded following any loading of the program into the computer.

" Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is i

permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

i 1

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

b

REACTIVITY CONTROL SYSTEM ROD SEQUENCE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.1.4.2 The rod sequence control system (RSCS) shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS I and 2*#, when THERMAL POWER is less l

than or equal to 20% RATED THERMAL POWER, the minimum allowable low power setpoint.

ACTION:

a.

With the RSCS inoperable:

1.

Control rod withdrawal for reactor startup shall not begin.

2.

Control rod movement shall not be permitted, ext.ept by a scram.

b.

With an irtoperable control rod (s), OPERABLE control rod movement may continue by bypassing the inoperable control rod (s) in the RSCS provided that:

1.

The position and bypassing of inoperable control rods is verified by a second licensed operator or other technically qualifled member of the unit technical staff, and 2.

There are not more than 3 inoperable control rods in any RSCS group.

SURVEILLANCE REQUIREMENTS 4.1.4.2 The RSCS shall be demonstrated OPERABLE by:

a.

Performance of a self-test prior to:

1.

Each reactor startup, and 2.

Rod inhibit mode automatic initiation when reducing THERMAL POWER.

b.

Attempting to select and move an inhibited control rod:

1.

After withdrawal of the first insequence control rod for each

(

reactor startup, and 2.

Within one hour after rod inhibit mode automatic initiation wnen reducing THERMAL POWER.

l l

"See Special Test Exception 3.10.2.

1. Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RSCS prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

I 53 LA SALLE - UNIT 2 3/4 1-17 Amendment No.

1 j

i 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH i

LIMITING CONDITION FOR OPERATION 3.9.1 The reactor mode switch shall be OPERABLE and locked in the Shutdown or Refuel position. When the reactor mode switch is locked in the Refuel position:

1 a.

A control rod shall not be withdrawn unless the Refuel position one-rod-out interlock is OPERABLE.

]

b.

CORE ALTERATIONS shall not be performed using equipment associated I

with a Refuel position interlock unless at least the following Refuel position interlocks are OPERABLE for such equipment, j

1.

All rods in.

2.

Refuel platform position.

3.

Refuel platform hoists fuel-loaded.

4.

Service platform hoist fuel-loaded, j

APPLICABILITY:

OPERATIONAL CONDITION 5*#

j ACTION:

j a.

With the reactor mode switch not locked in the Shutdown or Refuel position as specified, suspend CORE ALTERATIONS and lock ths raattor mode switch in the Shutdown or Refuel position.

b.

Pith the one-rod-out interlock inoperable, lock the reactor mode switch in the Shutdown position.

c.

With any of the above required Refuel position equipment interlocks inoperable, suspend CORE ALTERATIONS with equipment associated with the inoperable Refuel position equipment interlock.

" See Special Test Exceptions 3.10.1 and 3.10.3.##

1. The reactor shall be maintained in OPERATIONAL CONDITION 5 whenever fuel is i

in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

1. 1. The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch interlock functions provided that all control rods are verified to remain fully inserted by a second licensed operator or other technically qualified member of the unit technical staff.

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

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