Text

Amends 30 & 17 to Licenses NPF-11 & NPF-18,respectively, Revising Tech Specs Re APRM Gain Adjustment to Allow Time to Correct Calibr Before Declaring Channels Inoperable
	ML20137B672
Person / Time
Site:	LaSalle
Issue date:	11/20/1985
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20137B677	List: ML20137B672; ML20137B711;
References
	NUDOCS 8511260327
	Download: ML20137B672 (14)
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%,..... p COWONWEALTH EDIS0N C0fiPANY DOCKET N0. 50-373 LA SAI.LE COUNTY STATION, UNIT 1 AMENDPENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. fiPF-11 1.

The huclear Resulatory Comission (the Comission or the NRC) having found that:

A.

The application for amendment filed by the Cormonwealth Edison Company, dated August 28, 1985, complies with the standards and requirements of the Atenic Energy Act of 1954, as amended (the Act),

and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in ccnformity with the application, the provisions of the Act, and the regulations of the Comission; 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 activitics will be corducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Comission'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 attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:

(2) Technical SI:ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 30 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.

8511260327 851120 l

DR ADOCK 05000373 PDR llT

3.

This aneidrnent is effective as of date of issuance.

FOR THE NUCLEAR REGULATORY C0ft11SS10h Walter R. Butler, Chiet Licensing Branch No. 2 Division of Licensing

Enclosure:

^

Changes to the Technical Specifications Date of Issu6nce: 406 2 0 1985 s

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ENCLOSURE TO LICENSE AMENDMENT NO. 30 FACILil) CFERATING 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 vertical lines indicating the area of change.

REMOVE INSERT 3/4 2-3 3/4 2-3 3/4 3-1 3/4 3-1 3/4 3-5 3/4 3-5 3/4 3-8 3/4 3-8 e

4

.c 3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 4

i 3.2.2 The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased simulated thermal power-upscale control rod block trip setpoint (SRB) shall be established according to the following relationships:

a.

Two Recirculation Loop Operation S less than or equal to (0.66W + 51%)T S

less than or equal to (0.66W + 42%)T R8 b.

Single Recirculation Loop Operation S less than or equal to (0.66W + 45.7%)T S

less than or equal to (0.66W + 36.7%)T RB where:

S and S are in percent of RATED THERMAL POWER, R8 W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 108.5 million lbs/hr, T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER divided by the MAXIMUM FRACTION OF LIMITING POWER DENSITY. T is always less than or equal to 1.0.

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

ACTION:

With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased simulated thermal power-upscale control rod block trip setpoint set less conservatively than S or S correctiveactionwithin15minutesandrestNe,asabovedetermined, initiate S and/or S to within the RR required limits

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to Tess than 2E% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP and the MFLPD for each class of fuel shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and control rod block trip setpoint verified to be within the above limits or adjusted, as required:

a.

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

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating c.

with MFLPD greater than or equal to FRTP.

"With MFLPD greater than the FRTP up to 90% of RATED THERMAL POWER, rather than l

adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM readings are greater than or equal to 100% times MFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER, the required gain adjustment increment does not exceed 10% of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel.

LA SALLE UNIT 1 3/4 2-3 Amendment No. 30 4

1 7.,._...

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.

ACTION:

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

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

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

The provisions of Specification 3.0.4 are not applicable.

b.

With the the number of OPERABLE channels i c 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 CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1 1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic 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 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 specific reactor trip system.

A 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.

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

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

l l.y - -.

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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the channel in the tripped

[

condition provided at least one OPERABLE channel in the same 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 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 be automatically bypassed when turbine first stage pressure is < 140 psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

(j) Also actuates the EOC-RPT system.

Not required for control rods removed per Specifications 3.9.10.1 or j

3.9.10.2.

I LA SALLE - UNIT 1 3/4 3-5 Amendment No. 30

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TABLE 4.3.1.1-1 (Continued) 9 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL F

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH 7

FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED c

8.

Scram Discharge Volume Water I

Level - High NA M

R 1, 2, 5 a

i-a 9.

Turbine Stop Valve - Closure NA M

R 1

10.

Turbine Control Valve Fast j

C1csure Valve Trip System Oil i

Pressure - Low NA M

R*

1 l'

11.

Reactor Mode Switch Shutdown Position NA R

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

Manual Scram NA M

NA 1,2,3,4,5 w

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

1 (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 w

e'o 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.

j (d) This calibration shall consist of the adjustment of the APRM channel to conform to the power levels calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER. The APRM Gain ~ Adjustment Factor (GAF) for any channel shall be equal to the power value deter-mined by the heat balance divided by the APRM reading for that channel.

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 , (1) if power is greater than or equal to 90% of RATED THERMAL POWER and the APRM channel GAF is j

< 0.98, or (2) if pc'ver is less than 90% of RATED THERMAL POWER and the APRM reading exceeds the power value determined by the heat balance by more than 10% of RATED THERMAL POWER.

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

a, (e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a E

calibrated flow signal.

I g'

(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP 5

system.

5 (g) Measure and compare core flow to rated core flow.

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

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

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UNITED STATES NUCLEAR REGULATORY COMMISSION 3

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,y WASHINGTON, D. C. 20555 e

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COMMONWEALTH EDISON COMPANY-DOCKET NO. 50-374 LA SALLE COUNTY STATI0ft, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE AmendmentIo. 17 License No. NPF-18 1.

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

A.

The application for amendment filed by the Comonwealth Edison Company, dated August E8,1985, complies with the starc'erds and requirements cf the Atomic Energy Act of 1954, as amenoso (the Act),

ana the Ccmission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confonnity with the applicaticn, 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 cenducted without endangering the health and safety cf the public, and (ii) that such activities will be conducted in cenpliance with the Comission's regulaticns set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comen 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 regulatioris and all applicable requirenents have been satisfied.

2.

Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachraent to this license amendnient ar.d paragraph 2.C.(2) of Facility Operating License No. NPF 18 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Araendment Nc.17 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in ac:ordance with the Technical Specifications and the Envircomental Protection Plan.

~

2-3.

This amendment is effective as of date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Chief Licensing Branch No. 2 Division of Licensing

Enclosure:

Changes to the Technical Specifications i

Date of Issuance: NOV 2 0 EE6 i

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ENCLOSURE TO LICENSE AMENDMENT N0.17 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 3/4 2-3 3/4 2-3 3/4 3-1 3/4 3-1 i

3/4 3-5 3/4 3-5 3/4 3-8 3/4 3-8 i

9 I

5

POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased simulated thermal power-upscale control rod block trip setpoint (SRB) shall be established according to the following relationships:

a.

Two Recirculation Loop Operation S less than or equal to (0.66W + 51%)T

{

S less than or equal to (0.66W + 42%)T RB b.

Single Recirculation Loop Operation S less than or equal to (0.66W + 45.7%)T S

less than or equal to (0.66W + 36.7%)T RB where: S and S are in percent of RATED THERMAL POWER, RB W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 108.5 million 1bs/hr, T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER f

divided by the MAXIMUM FRACTION OF LIMITING POWER DENSITY. T is always less than or equal to 1.

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

ACTION:

With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased simulated thermal power upscele control rod block trip setpoint set less conservatively than S or S correctiveactionwithin15minutesandresthe,asabovedetermined, initiate S and/or S to within the R

requiredlimits*within2hoursorreduceTHERMALPOWERto$essthan25%of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP and the MFLPD for each class of fuel shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and control rod block trip setpoint verified to be within the above limits or adjusted, as required:

a.

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

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and c.

Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with MFLPD greater than or equal to FRTP.

With MFLPD greater than the FRTP up to 90% of RATED THERMAL POWER, rather than

{

adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM read-ings are greater than or equal to 100% times MFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER, the required gain adjustment increment does not exceed 10% of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel.

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

l l

l 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INST'RUMENTATION 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.

ACTION:

With the number of OPERABLE channels less than required by the Mini-a.

[

mum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channels and/or trip system in the tripped con-l dition* within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The provisions of Specification 3.0.4 are not applicable.

b.

With'the 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 I

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

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

l 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shell be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one l

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 specific reactor trip system.

With a design providing only one channel per trip system, an inoperable char.nel 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 l

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, excs, " when this would cause the Trip Function to occur.

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

7 V

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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the channel in the tripped condition l

provided at least one OPERABLE channel in the same 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 leve~1 or less than 14 LPRM 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 be automatically bypassed when turbine first stage pressure is < 140 psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

(j) Also actuates the EOC-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.17

TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMEN1ATION SURVEILLANCE REQUIREMENTS

'N CHANNEL OPERATIONAL E

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH 1

i FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

E 8.

Scram Discharge Volume Water

. y Level - High NA M

R 1,2,5 1

9.

Turbine Stop Valve - Closure NA M

R 1

10.

Turbine Control Valve Fast Closure Valve Trip System 011 Pressure - Low NA M

R 1

l 11.

Reactor Mode Switch Shutdown Position NA R

NA 1,2,3,4,5 l

12.

Manual Scram NA M

NA 1,2,3,4,5

13. Control Rod Drive i

a.

Charging Water Heade-I Pressure - Low NA M

R 2, 5 Q

b.

Delay Timer NA M

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

ilo (b) The IRM, and SRM channels shall be determined to overlap for at least 1/2 decades during each startup and the IRM i

and APRM channels shall be determined to overlap for at least 1/2 decades during each controlled shutdown, if not h

perfomed within the previous 7 days.

i (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 power levels calculated by

{

a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER. The APRM Gain Adjustment Factor (GAF) for any channel shall be equal to the power value determined by the heat balance divided j

by the APRM reading for that channel.

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 , 3

(1) if power is greater than or equal to 90% of RATED THERMAL POWER and the APRM channel GAF is < 0.98, or (2) if power is less than 90% of RATED THERMAL POWER and the APRM reading exceeds the power value determined by the i

heat balance by more than 10% of RATED THERMAL POWER.

Until any required APRM adjustment has been accomplished, i

E 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 5

signal.

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

(g) Measure and compare core flow to rated core flow.

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

ML20137B672

Text

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