Text

Amends 130 & 114 to Licenses NPF-11 & NPF-18,respectively, Revising TS to Lower Power Level (from 30% to 25% Rated Thermal Power) Below Which TCV & TSV Closure Scram Signals & end-of Cycle Recirculation Pump Trip Signal Not in Effect
	ML20203H922
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Site:	LaSalle
Issue date:	02/12/1999
From:	Skay D; NRC (Affiliation Not Assigned)
To:	;
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ML20203H928	List: ML20203H922; ML20203H932;
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	NUDOCS 9902230153
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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20006 4001

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASAI I F COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

130 License No. NPF-11 1.

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

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 16,1998, 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 authorized 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-11 is hereby amended to read as follows:

a l

i 9902230153 990212 i

PDR ADOCK 05000373 P

PDR

(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 130

. 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 license amendment is effective as of the date of its issuance ano chc!! be implemented within 90 days.

i FOR THE NUCLEAR REGULATORY COMMISSION W

Donna M. Skay, Project M ager Project Directorate 111-2 Division of Reactor Projects - lilllV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: February 12, 1999 4

l l

i

ATTACHMENT TO LICENSE AMENDMENT NO. 130 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-8 3/4 3-8 3/4 3-39 3/4 3-39 s

3/4 3-40 3/4 3-40 3/4341 3/4341 3/4 3-44 3/4 3-44 8 3/4 3-3 B 3/4 3-3 t

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TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 2 -

Verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.

ACTION 3 -

Suspend all operations involving CORE ALTERATIONS

and insert all insertable control rods within one hour.

ACTION 4 -

Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 5 -

Deleted ACTION 6 -

Initiate a reduction in THERMAL POWER within 15 minutes and reduce THERMAL POWER to less than 25% of RATED THERMAL POWER, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 7 -

Verify all insertable control rods to be inserted within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 8 -

Lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 9 -

Suspend all operations involving CORE ALTERATIONS,* and insert all insertable control rods and lock the reactor mode switch in the SHUTDOWN position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

'Except movement of IRM, SRM or special movable detectors, or replacement of LPRM strings provided SRM instrumentation is OPERABLE per Specification 3.9.2.

LA SALLE - UNIT 1 3/4 3-4 Amendment No.130

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance without placing the channel in the tripped condition provided at least one OPERABLE channel in the sacee trip system is monitoring that parameter.

(b) The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn

and during shutdown margin demonstrations performed per Specification 3.10.3.

(c) An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.

(d) This function is not required to be OPERABLE when the reactor pres =ure vessel head is unbolted or removed per Specification 3.10.1.

(e) This function shall be automatically bypassed when the reactor mode switch is not in the Run position.

(f)

This function is.not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(g) Also actuates the standby gas treatment system.

(h) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(i)

This function shall not be automatically bypassed when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

(j)

Also actuates the EOC-RPT system.

'Not required for control rv temoved per Specifications 3.9.10.1 or 3.9.10.2.

l.A SALLE - UNIT 1 3/4 3-5 Amendment No.130

~.

I TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

CHANNEL OPERATIONAL l

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH l

FUNCTIONAL UNIT CHECK TEST CALIBRAT6ON SURVEILLANCE REQUIRED 4

i 8.

Scram Discharge Volume Water Level-High NA Q

R 1, 2, 5 9.

Turtune Stop Valve - Closure

NA Q

R 1

l j

10.

Turtune Control Valve Fast l

Closure Valve Trip System Oil Pressure - Low 8 NA Q

R 1

l i

I 11.

Reactor Mode Switch l

i Shutdown Position NA R

NA 1,2,3,4,5 12.

Manual Scram NA W

NA 1,2,3,4,5 13.

Control Rod Dnve a.

Charging Water Header Pressure - Low NA M

R 2, 5 I

b.

Delay Timer NA M

R 2, 5 (a)

Neutron detectors may be excluded from CHANNEL CAllBRATION.

(b)

The IRM and SRM channels shall be determined to overlap for at least 1/2 decades dunng each startup and the IRM and APRM j

channels shall be determined to overlap for at least 1/2 decades dunng each controlled shutdown, if not performed within the previous 7 days.

(c)

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.

(d)

This cahbration shall consest of the adjustment of the APRM channel to conform to the power levels calculated by a heat balance dunng OPERATIONAL CONDITION 1 when THERMAL POWER 2 25% of RATED THERMAL POWER. The APRM Gain j

Adjustment Factor (GAF) for any channel shall be equal to the power value determined by the heat balance divided by the APRM reading for that channel.

1 i

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , adjust any APRM channel with a GAF > 1.02. In addition, adjust any APRM chcr.nel within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , if power is j

greater than or equal to 90% of RATED THERMAL POWER and the APRM channel GAF is < 0.98. Until any required APRM adjustment has been accomplished, notification shall be posted on the reactor control panel.

(e)

This cabbration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.

(f)

The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH).

(g)

Measure end compare core flow to rated core flow.

(h)

This calibration shall consist of ven'fying the 6 i 1 second simulated thermal power time constant.

(i)

At least once per 18 months, verify Turtune Stop Valve - Closure and Turbine Control Valve Fast Closure Valve Trip System Oil Pressure - Low Trip Functions are not bypassed when THERMAL POWER is > 25% of RATED THERMAL POWER.

l Specification 4.0.2 applies to this 18-month interval.

The provisions of Specification 4.0.4 are not applicable for a penod of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering OPERATIONAL CONDITION 2 or 3 when shutting down from OPERATIONAL CONDITION 1.

LA SALLE - UNIT 1 3/4 3-8 Amendment No.130

INSTRUMENTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

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

6PPRCABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

l ACTION:

With an end-of-cycle recirculation pump trip system instrumentation channel trip a.

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 OPERAELE 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 nPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition w' thin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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:

i 1.

If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 4

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 RATIO (MCPR) Limiting Condition for Operation (LCO) to the EOC-RPT inoperable value per Specification 3.2.3 within the next i hour or, 2.

Reduce THERMAL POWER to less than 25% of RATED THERMAL POWER l

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With both trip systems inoperable, restore at least one trip system to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Otherwise, either:

LA SALLE - UNIT 1 3/4 3-39 Amendment No.130

INSTRUMENTATION END-OF-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 EOC-RPT inoperable value per Specification 3.2.3 within the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or, 2.

reduce THERMAL POWER to less than 25% of RATED THERMAL FOWER 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-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME of each trip function shown in Table 3.3.4.2-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least the logic of one type of channel input, turbine control valve fast closure or turbine stop valve closure, such that both types of channel inputs are tested at least once per 36 months. The time allotted for breaker arc suppression shall be verified by test at least once per 60 months.

I l

LA SALLE - UNIT 1 3/4 3-40 Amendment No.130

TABLE 3.3.4.2-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION l

MINIMUM OPERABLE CHANNELS l

TRIP FUNCTION PER TRIP SYSTEM

1.

Turtune Stop Valve Closure 2N 2.

Turbine Control Valve - Fast Closure 2*

(a) A trip system may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided that the other trip system is OPERABLE.

l (b) This function shall not be automatically bypassed when THERMAL POWER is greater than or equal to 25% of RATED l

THERMAL POWER.

i I

i LA SALLE - UNIT 1 3/4 3-41 Amendment No.130

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TABLE 4.3.4.2.1-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVElLLANCE REQUIREMENTS CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION TEST CAllBRATION 1

1.

Turbine Stop Valve-Closure" Q

R l

2.

Turbine Control Valve-Fast Closure" Q

R l

L I

I t

(a) At least once per 18 me ans, venfy Turbine Stop Valve - Closure and Turbine Control Valve - Fast Closure Trip Functions are not bypassed when THERMAL POWER is >25% of RATED THERMAL POWER. Specificahon 4.0.2 applies to this 18-month interval.

l i

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LA SALLE - UNIT 1 3/4 3-44 AMENDMENT NO.130

INSTRUMENTATION BASES t

3/4.3.4 REClRCULATION PUMP TRIP ACTU1 TION INSTRUMENTATION i

The anticipated transient without scram (A1WS) recirculation pump trip system provides a means of !imiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the

{

envelope of study events in General Electric Company Topical Report NEDO-1034g, dated j

March 1971 and NEDO-24222, dated December,1979, and Appendix G of the FSAR.

The end-of-cycle recirculation pump trip (EOC-RPT) system is a part of the Reactor Protection System and is an essential safety supplement to the reactor trip. The purpose of the EOC-RPT is to recover the loss of thermal margin which occurs at the end-of-cycle. The physical phenomenon involved is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity. Each EOC-RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting pressurization events. The two events for which the EOC-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine control valves.

Analyses were performed to support continued operation with one or both trip systems of the EOC-RPT inoperable. The analyses provide MINIMUM CRITICAL POWER RATIO (MCPR) values which must be used if the EOC-RPT system is inoperable. These MCPR limits are included in the COLR and ensure that adequate margin to the MCPR safety limit exists with the EOC-RPT function inoperable. Application of these limits are discussed further in the bases for Specification 3.2.3.

A fast closure sensor from each of two turbine control valves provides input to the EOC-RPT system; a fast closure sensor from each of the other two turbine control valves provides input to the second EOC-RPT system. Similarly, a position switch for each of two turbine stop valves provides input to one EOC-RPT systern; a position switch from each of the other two stop valves provides input to the other EOC-RPT system. For each EOC-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for the fast closure of turbine control valves and a 2-out-of-2 logic for the turbine stop valves. The operation of either logic will actuate the EOC-RPT system and trip both recirculation pumps.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled. The manual bypasses and the automatic Operating Bypass at less than 25% of RATED THERMAL POWER are annunciated in the control room.

l Specified surveillance intervals and surveillance and maintenance outage times have been

. determined in accordance with the following:

1.

NEDC-30851P-A, " Technical Specification Improvement Analyses for BWR Reactor Protection System", March 1988.~

LA SALLE - UNIT 1 B 3/4 3-3 Amendment No.130 1

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4 UNITED STATES

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NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 30066-0001

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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. NPF-18 1.

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

A.

The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 16,1998, complies wkh the standards and i

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 authorized 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 1

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-18 is hereby amended to read as follows:

l,

l (2)

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through i

Amendment No. 114, 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 license amendment is effective as of the date of its issuance and shall be implemented prior to startup of L2C8.

FOR THE NUCLEAR REGULATORY COMMISSION I

C>c"&

Donna M. Skay, Project Man er Project Directorate 111-2 Division of Reactor Projects -Ill/IV Office of Nuclear Reactor Regulation

Attachment:

l Changes to the Technical l

Specifications Date of issuance: February 12, 1999 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 114 FACILITY OPERATING LICENSE NO NPF-18 DOCKET NO. 50-374 Replace the following pages of ttie Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of :,hange. The page indicated by an asterisk (*) is provided for convenience only.

REMOVE INSERT 3/434 3/434 3/4 3-5 3/4 3-5 3/4 3-8 3/4 3-8 3/4 3-39 3/4 3-39 3/4 3-41 3/4 3-41 3/4 3-43*

3/4 3-43*

3/4 3-44 3/4 3-44 B 3/4 3-3 8 3/4 3 3 l

1 i

i 1

i

- - - - =

l l

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION STATEMENTS ACTION 1 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 2 Verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 3 Suspend all operations involving CORE ALTERATIONS

and insert all insertable control rods within one hour.

ACTION 4 Be in at least STARTUP within 6 hou%

ACTION 5 DELETED ACTION 6 Initiate a reduction in THERMAL POWER within 15 minutes and reduce THERMAL POWER to less than 25% of RATED THERMAL POWER.

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

ACTION 7 Verify all inserteble control rods to be inserted within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 8 Lock the reacto mode switch in the Shutdown position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 9 Suspend all operations involving CORE ALTERATIONS.* and insert all insertable control rods and lock the reactor mode switch in the SHilTDuWN position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

1 l

Exceat movement of IRM, SRM, or special movable detectors, or replacement of L3RM strings provided SRM instrumentation is OPERABLE per Specification 3.9.2.

LA SALLE - UNIT 2 3/4 3-4 Amendment No.114

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for i

required surveillance without ) lacing the channel in the tripped condi-tion provided at least one OPEMBLE channel-in the same trip system is monitoring that parameter.

i (b) The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn

and during shutdown margin demonstrations performed per Specification 3.10.3.

(c) An APRM channel is inoyerable if there are less than 2 LPRM inputs per i

level or less than 14 _PRM inputs to an APRM channel.

(d) This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.

(e) This function shall be automatically bypassed when the reactor mode switch is not in the Run position.

-(f) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(g) Also actuates the standby gas treatment system.

(h) With any control rod withdrawn.

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

(i) This function shall not be automatically bypassed when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

(j) Also actuates the E0C-RPT system.

Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

LA SALLE - UNIT 2 3/4 3-5 Amendment No.114

TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE RE0VIRED 8.

Scram Discharge Volume Water Level - Higfi NA Q

R 1, 2. 5

,o

]

9.

Turbine Stop Valve - Closurt NA 0

R 1

l

10. Turbine Control Valve Fast ClosureValveJgipSystemOil Pressure - Low NA Q

R 1

1

11. Reactor Mode Switch i

Shutdown Position NA R

NA 1.2.3.4.5

12. Manual Scram NA W

NA 1.2.3.4.5

13. Control Rod Drive a.

Charging Water Header Pressure - Low NA M

R

2. 5 b.

Delay Timer NA M

R

2. 5 (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decades during each startup and the IRM and APRM channels shall be determined to overlap for at least 1/2 decades during each con-trolled shutdown, if not performed within the previous 7 days.

(c) 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.

(d) This calibration shall consist of the adjustment of the APRM channel to conform to the Dower levels calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER 2 25% of RATED THERMAL mined by the heat balance divided by the APRM reading for that channel. qual to the power value deter-POWER. The APRM Gain Adjustment Factor (GAF) for any channel shall be e Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , adjust any APRM channel with a GAF > 1.02.

In addition adjust any APRM channel within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , if power is greater than or equal to 90% of RATED THERMAL POWER and the APRM channel GAF is

< 0.98.

Until any required APRM adjustment has been accomplished notification shall be posted on the reactor control panel.

(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH).

(

Measure and compare core flow to rated core flow.

(g) This calibration shall consist of verifying the 6 1 second simulated thermal power time constant.

h)

(1) At least once per 18 months. verify Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure Valve Trip System Oil Pressure - Low Trip Functions are not bypassed when THERMAL POWER is > 25% of RATED THERMAL POWER. Specification 4.0.2 applies to this 18-month interval.

The provisions of Specification 4.0.4 are not applicable for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after entering OPERATIONAL CONDITION 2 or 1 when shutting down from OPERATIONAL CONDITION 1.

LA SALLE - UNIT 2 3/4 3-8 Amendment No. 114

TNSTRUMENTATION END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.2 The end-of-cycle recirculation Jump trip (E0C-RPT) system instrumenta-tion channels shown in Table 3.3.4.2-1 s1all be OPERABLE with their trip setpoints set consistent with the values shown in the Tri) Setpoint column of Table 3.3.4.2-2 and with the END-0F-CYCLE RECIRCULATION PJMP 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 25% of RATED THERMAL POWER.

ACTION:

a.

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

b.

With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems place the inoperable channel (s) in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 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 inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or 2.

Reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With both trip systems inoperable, restore at least one trip system to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . otherwise, either:

1.

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

.fication 3.2.3 within the next 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or 2.

Reduce THERMAL POWER to less than 25% 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.114

TABLE 3.3.4.2-1 a

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION MINIMUM l

OPERABLECHANNEg

' TRIP FUNCTION PER TRIP SYSTEM l

4 j

1.

Turbine Stop Valve Closure 2(b) l 2.

Turbine Control Valve - Fast Closure 2(b) l I

i i

j i

i t

t i

s (a) A trip system may be placed in an ino:erable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided that the other trip system is OPERABLE.

(b) This function shall not be automatically bypassed when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

4 4

?

i 4

LA SALLE - UNIT 2 3/4 3-41 Amendment No.114

l TABLE 3.3.4.2-3 5

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME f

.?

i;;-

0 l

TRIP FUNCTION RESPONSE TIME (Milliseconds) czU 1.

Turbine Stop Valve-Closure 1 97 w

2.

Turbine Control Valve - Fast closure i 97 r

I W

i r

I i

TABLE 4.3.4.2.1-1 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION TEST CALIBRATION 1.

Turbine Stop Valve Closure"'

0 R

l i

2.

Turbine Control Valve-Fast Closure"'

0 R

l

'I E

i i

(a)

At least once per 18 months. verify Turbine Stop Valve - Closure and Turbine Control Valve - Fast Closure Trip Functions are not bypassed when THERMf1 POWER is > 25% of RATED THERMAL POWER.

l Specification 4.0.2 applies to this 18-month interval.

i i

I i

1 LA SALLE - UNIT 2 3/4 3-44 AMENDMENT N0.114 l

m

.m

m. -.

l l

INSTRUMENTATION BASES 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION (continued)

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P-A, " Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation instrumentation)", Parts 1 and 2, December 1988, and RE-025 Revision 1, " Technical Specification improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for LaSalle County Station, Units 1 and 2", April 1991. When a channel is placed in an inoperable status solely for performance of required surveillances, entry into LCO and required ACTIONS may be delayed, provided the associated function maintains ECCS initiation capability.

3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient without scram (ATWS) recirculation pump trip system provides a means oflimiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NEDO-10349, dated March 1971 and NEDO-24222, dated December,1979, and Appendix G of the FSAR.

The end-of-cycle recirculation pump trip (EOC-RPT) system is a part of the Reactor Protection System and is an essential safety supplement to the reactor trip. The purpose of the EOC-RPT is to recover the loss of thermal margin which occurs at the end-of-cycle. The physical phenomenon involved is that tne void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity. Each EOC-RPT system trips both recirculation pumps, reducing coolant flow in order to reduce the void collapse in the core during two of the most limiting pressurization events. The two events for which the EOC-RPT protective feature will function are closure of the turbine stop valves and fast closure of the turbine control valves, i

i Analyses were performed to support continued operation with one or both trip systems of the EOC-RPT inoperable. The analyses provide MINIMUM CRITICAL POWER RATIO (MCPR) values which must be used if the EOC-RPT system is inoperable. These MCPR limits are included in the COLR and ensure that adequate margin to the MCPR safety limit exists with the EOC-RPT function inoperable. Application of these limits are discussed further in the bases for Specification 3.2.3.

A fast closure sensor from each of two turbine control valves provides input to the EOC-RPT system; a fast closure sensor from each of the other two turbine control valves provides input to the second EOC-RPT system. Similarly, a position switch for each of two turbine stop valves provides input to one EOC-RPT system; a position switch from each of the other two stop valves provides input to the other EOC-RPT system. For each EOC-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for the fast closure of turbine control valves and a 2-out-of-2 logic for the turbine stop valves. The operation of either logic will actuate the EOC-RPT system and trip both recirculation pumps.

Each EOC-RPT system may be manually bypassed by use of a keyswitch which is administratively controlled. The manual bypasses and the automatic Operating Bypass at less than 25% of RATED THERMAL POWER are annunciated in the control room.

l LA SALLE - UNIT 2 B 3/4 3-3 Amendment No.114

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