Text

Proposed Tech Spec,Addressing Allowable APRM Gain Adjustment Factors & Clarifying Wording of Two Addl Specs. NSHC Encl
	ML20134N103
Person / Time
Site:	LaSalle
Issue date:	08/28/1985
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20134N100	List: ML20134N099; ML20134N103;
References
	NUDOCS 8509050005
	Download: ML20134N103 (12)
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ATTAC E NT B i

PROPOSED CHANGE TO APPENDIX A J

, TECHNICAL SPECIFICATION TO OPERATING LICENSES WF-ll and WF-18 l

s Revised Pages:

i WF-ll NPF-18 3/4 2-3 3/4 2-3 3/4 3-1 3/4 3-1 j 3/4 3-5 3/4 3-5

} 3/4 3 3/4 3-8 4

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POWER DISTRIBUTION LIMITS l l

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 18

b. Single Recirculation Loop Operation 5 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, DB 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 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, S and/or S Ra to within initiate the 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 25% 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:

i 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.

l "With MFLPD greater than the FRTP & W ::u q__;;; = u m up to 90% of RATED l THERMAL POWER, rather than 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. 18 l

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3/4.3 INSTRUMENTATION ,

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR CPERATION 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:

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

%, 4 4 OPERABLE Channels per Trip System requirement for one trip system, place A m ,.a. .Wwrt trip system in the tripped condition

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

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 13 months. Each test shall include at least one channel per trip systes such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.

"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 jn 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 1 ,

3/4 3-1 Amcodment No. 18

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS

, (a) A channel may be placed in sn inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for _y[hgyy,jL, required surveillance without placing the " " - y-- " in the tripped i 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 17 +.here 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 oe 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 t

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 lgg RATED THERMAL POWER.

(j) Also actuates the EOC-RPT system.

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

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

l TABLE 4.3.1.1-1 (Continued) 9 m REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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OPERATIONAL E CHANNEL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH e FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED H 8. Scram Discharge Volume Water H Level - High NA M R 1, 2, 5

9. Turbine Stop Valve - Closure NA M R 1

10. Turbine Control Valve Fast Closure Valve Trip System Oil

- Pressure - Low NA M R 1

-11. Reactor Mode Switch Shutdown Position NA R NA 1,2,3,4,5 1,2,3,4,5

$ 12. Manual Scram NA M NA Y

(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 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) is calibration 11 consist of adjustment of APRM channel to c rm to the power lud s ca ulated by ea balance dur g0 RATIONAL C ITI 1 when THE ~> 25% of RA THE L POWE . Adjus the AP r.hanne if the solute d erence i greater t n 2%. y APRM gullsA chann ga adjustmen made n complian wi Specificatio .2. shall not be c ed in y deterni the absolute ference.

(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) 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.

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INSERT FOR PAGE 3/4 3-8 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 2 25% of RATED THERMAL i POWER. The APRM Gain 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.

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 TERMAL POWER and the APRM channel GAF is4 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 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.

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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

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

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

RB less than or equal to (0.66W + 36.7%)T where: 5 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 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.

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 correctiveactionwithin15minutesandresthe,asabovedetermined, 5 and/or S to within initiate the required limits

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER toNess 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 .

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.

Y "With MFLPD greater than the FRTP =he m =:=iry up to 90% of RATED THER- I MAL POWER, rather than adjusting the APR4 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 2 3/4 2-3

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:

a. With the number of OPERABLE channels less than required by the 3 Minimum OPERABLE Channels per Trip System requirement for one trip

/ system, place M trip system in the tripped condition

within l cOLxvvv43hL 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The p'rovisions 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 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 funct'ional 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.

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.

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

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 gjQoj,,,3f[,

required surveillance without placing the crin :y;r== 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.

J (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 5 140 psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

(j) Also actuates the EOC-RPT system.

CNot 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. 4

TABLE 4.3.1.1-1 (C:ntinued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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TABLE 4.3.1.1-1 (Continued) .

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REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CNANNEL OPERATIONAL E CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR MlICH Z FUNCTIONAL UNIT Cl!ECK TEST CALIBRATION SURVEILLANCE REQUIRED to ,

8. Scram Discharge Volume Water Level - High NA M R 1, 2, 5 ,

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 w 11. Reactor Mode Switch

) Shutdown Position NA R NA 1,2,3,4,5 w ,

c'. 12. Manual Scram NA M NA 1,2,3,4,5 i

13. Control' Rod Drive

a. Charging Water Header Pressure - Low NA M R 2, 5 4

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 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 start , if not performed within the previous 7 days.

l (d) s cslibration shall consi f the adjustment of t PRM channel to ora to the power v

> 25% of RAT e

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a1 lated by a heat bal e dur OPERATIONAL CO 10 olute di when THE P rence is/ greater -an 2%. AnfAPRM MM g rHE POWER. Adjus he APRM ch 1 if the

! :hannel n adj nt made in comp ce wi Specification .2. shall not be clude in 1 j', determining absolute difference.

2 (e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a P calibrated flow 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. l (h) This calibration shall consist of verifying the 6 i I second simulated thermal power time constant.

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INSERT FOR PAGE 3/4 3-8 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 .h 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 by the APRM reading for that chamel.

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 TKRMAL POWER and the APRM channel GAF. is 4 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 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.

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ATTACINENT C

Significant Hazards Consideration i

l Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. . Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Unit 1 and 2 in accordance with the proposed amendment will not:

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1) Involve a significant increase in the probability or consequences of I an accident previously evaluated because this change is simply a t

clarification. The APRM channel setpoints will be maintained within required limits (or restored to proper limits ~with the time limits

consistent with other specifications).

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2) Create the possibility of a new or different kind of accident from l*

any accident previously evaluated because no change in the APRM scram function is included in this amendment.

t

3) Involve a significant reduction in the margin of safety because the change does not allow the APRMs to be set non-conservative.

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. . Therefore, based on the guidance provided in the Federal Register and the criteria

, established in 10 CFR 50.92(e), the proposed change does not' constitute a significant hazards consideration.

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ML20134N103

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