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Proposed Tech Specs,Consisting of Change Request 174, Extending Surveillance Interval for Rtbs from Monthly to Quarterly & Increasing AOT for Operation W/Inoperable Rtb from One H to Two H
	ML20116D012
Person / Time
Site:	Waterford
Issue date:	07/17/1996
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20116D010	List: ML20116D007; ML20116D012;
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	NUDOCS 9608010271
	Download: ML20116D012 (14)
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NPF-38-174 l 1

ATTACHMENT A 1

9608010271 960717 PDR ADOCK 05000382 P PDR

TABLE 3.3-1 (Continued)

! ACTION STATEMENTS k . ' 2. Pressurizer Pressure - Pressurizer Pressure - High i High Local Power Density - High j DNBR - Low '

3. Containment Pressure - Containment Pressure - High (RPS) High Containment Pressure - High (ESF)

4. Steam Generator

Steam Generator Pressure - Low Pressure - Low Steam Generator AP 1 and 2 j

(EFAS 1 and 2)

5. Steam Generator Level Steam Generator Level - Low Steam Generator Level - High Steam Generator AP (EFAS). ,

! 6. Core Protection Local Power Density - High !

l Calculator DNBR - Low J

j STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST. Subsequent l' STARTUP and/or POWER OPERATION may continue if one channel is j

restored to OPERABLE status and the provisions of ACTION 2 are

! satisfied.

i ACTION 4 -

With the number of channels OPERABLE one less than required by j

the Minimum Channels OPERABLE requirement, suspend all operations l involving positive reactivity changes.

ACTION 5 -

. With.the number of channels OPERABLE one less those required by i

the Minimum Channels OPERABLE requirement, STARTUP and/or POWER l OPERATION may continue provided the reactor trip breakers of i

the inoperable channel are placed in the tripped condition l within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; otherwise, be in al. least HOT STANDBY within i 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to I hour j for surveillance testing per Specification 4.3.1.1.

! ACTION 6 -

a. With one CEAC inoperable, operation may continue for up to 7 days provided that at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , each CEA j

j is verified to be within 7 inches (indicated position) of i

all other CEAs in its group.

b. With both CEACs inoperable, operation may continue provided

.- that:

l

1. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the DNBR margin required by Specification 3.2.4b (COLSS in service) or 3.2.4d j

(COLSS out of service) is satisfied and the Reactor l

Power Cutback System is disabled, and 1

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l WATERFORD - UNIT 3 3/4 3-6 AMENDMENT NO. 5

~ . - _ - - . - _ . . .. - .~._ _ .- --- -. - . . .. .. .- - . . . -...

I c TABLE 4.3-1 O

g REACTOR PROTECTIVE INSTRUNENTATION SURVEILLANCE REQUIREE NTS n

o -

B l CHANNEL MODES FOR WHICH

' CHANNEL CHANNEL FUNCTIONAL UNIT CHECK CALIBRATION FUNCTIONAL TEST SURVEILLANCE IS REQUIREO v 1. Manual Reactor Trip ,

N.A. N.A. R and S/U(1) 1, 2, 3*, 4*, 5*

2. Linear Power Level - High S O(2,4),M(3,4), Q 1, 2 Q(4) !

3. Logarithmic Power Level - High S R(4) Q and S/U(1) 28, 3, 4, 5 I

4. Pressurizer Pressure - High S R Q 1, 2

5. Pressurizer Pressure - Low 5 R Q 1, 2

[ 6. Containment Pressure - High S R

, Q 1, 2 E 7. Steam Generator Pressure - Low 5 R Q 1, 2

8. Steam Generator Level - Low S R Q 1, 2

9. Local Power Density - High 5 0(2,4),R(4,5) Q,R(6) 1, 2

10. DNBR - Low S(7),O(2,4),

S Q,R(6) 1, 2 M(8),R(4,5)

11. Steam Generator Level - High S R Q 1, 2 E 12. Reactor Protection System .

$ Logic N.A. N.A. Q and S/U(1) 1, 2, 3*, 4*, 5*

5 x 5

. . i g TA8LE 4.3-1 (Continued) !

C .

g REACTOR PROTECTIVE INSTRUNENTATION SURVEILLANCE REQUIRESENTS 2

8 -

CNAfGEL IWDES FOR WHICH ,

c CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 5 FUNCTIONAL UNIT CHECK CALIBRATION TEST ;

15 REQUIRED w 13. Reactor Trip Breakers N.A. M.A.

N(10),S/U(1) 1, 2, 3* , 4* , 5* . !

14. Core Protection Calculators S D(2,4),R(4,5) Q(9),R(6) 1, 2 }

15. CEA Calculators S R Q,R(6) ' '

1, 2

16. Reactor Coolant Flow - Low 5 R 1, 2 Q

R. -

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TABLE 4.3-1 (Continued)

TABLE NOTATIONS i -

With the reactor trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

l fThe provisions of Specificatig'g 4.0.4 are not applicable when reducing reactor power to less than }9 '% of RATED THERMAL POWER from a reactor j power level grgater than 10 % of RATED THERMAL POWER.

i Upon reducing power below 10 % of RATED THERMAL POWER, a CHANNEL FUNCTIONAL TEST shall l

be perfomed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if not performed during the previous 31 days.

s This requirement does not apply with the reactor trip breakers open.

(1) Each startup or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.

(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 15% !

of RATED THERMAL POWER: adjust the Linear Power Level signals and the j CPC addressable constant multipliers to make the CPC AT power and CPC i j nuclear power calculations agree with the calorimetric calculation if '

i absolute difference is greater than 25. During PHYSICS TESTS, these j daily calibrations may be suspended provided these calibrations are '

performed upon reaching each major test power plateau and prior to proceeding to the next majnr test power plateau.

(3) Abov~e15%ofRATEDTHERMALPOWER,verifythattheline**Sowersub-l channel gains of the excore detectors are consistent t

he values used to establish the shape annealing matrix elements m .he Core?

l Protection Calculators. '

i (4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

k (5) After each fuel loading and prior to exceeding 70% of RATED THERMAL i

POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements.

(6) This CHANNEL FUNCTIONAL TEST shall include the injection of simulated l process signals into the channel as close to the sensors as practicable j to verify OPERABILITY including alars and/or trip functions.

} (7) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate 1

I as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate. The flow measurement uncertainty is included in the BERR1 term in the CPC and is equal to or greater than 4%.

(8) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by calorimetric calculations.

(9) The quarterly CHANNEL FUNCTIONAL TEST shall include verification that l the correct values of addressable constants are installed in each OPERABLE CPC.

(10) At least once per lo months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage trip function and the shunt trip function.

WATERFORD - UNIT 3 3/4 3-12 AMENDMENT NO. 48.69

3/4.3 INSTRUMENTATION !

BASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES l ACTUATION SYSTEMS INSTRUMENTATION l The OPERABILITY of the Reactor Protective and Engineered Safety Features Actuation Systems instrumentation and bypasses ensures that (I) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of l service for testing or maintenance, and 4 capability is available from diverse para (me)ters. sufficient system functional t

The OPERABILITY of these systems is required to provide the overall

! reliability, redundancy, and diversity assumed available in the facility i design for the protection and mitigation of accident and transient conditions.

! The integrated operation of each of these systems is consistent with the l assumptions used in the safety analyses.

l The redundancy design of the Control Element Assembly Calculators (CEAC)

{ provides reactor protection in the event one or both CEACs become inoperable.

If one CEAC is in test or inoperable, verification of CEA position is ,

! performed at least every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . If the second CEAC fails, the CPCs will use j DNBR and LPD penalty factors to restrict reactor operation to some maximum i fraction of RATED THERMAL POWER. If this maximum fraction is exceeded, a ,

i reactor trip will occur. !

/

l The Surveillance Requirements specified for these systems ensure that the !

! overall system functional capability is maintained comparable to the original l design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. The quarterly fre- {

quency for the channel functional tests for these systems comes from the l analyses presented in topical report CEN-327: RPS/ESFAS Extended Test Interval Evaluation,. as supplemented.

l:

RPS\ESFAS Trip Setpoints values are determined by means of an explicit setpoint calculation analysis. A Total Loop Uncertainty (TLU) is calculated for each RPS/ESFAS instrument channel. The Trip Setpoint is then determined by adding or subtracting the TLU from the Analytical Limit (add TLU for i decreasing process value; subtract TLU for increasing process value). The

[

i Allowable Value is determined by adding an allowance between the Trip Setpoint and the Analytical Limit to account for RPS/ESFAS cabinet Periodic Test Errors

! PTE) which are present during a CHANNEL FUNCTIONAL TEST. PTE combines the RPS/ESFAS cabinet reference accuracy, calibration equipment errors (M&TE), and i RPS/ESFAS cabinet bistable Drift. Periodic testing assures that actual

' setpoints are within their Allowable Values. A channel is inoperable if its actual setpoint is not within its Allowable Value and corrective action must 3 be taken. Operation with a trip set less conservative than its setpoint, but q within its specified ALLOWABLE VALUE is acceptable on the basis that the difference between each trip Setpoint and the ALLOWABLE VALUE is equal to or l 1ess than the Periodic Test Error allowance assumed for each trip in the j safety analyses. '

i, i

WATERFORD - UNIT 3 B 3/4 3-1 Amendment No. 69,113

i 3/4.3 INSTRUMENTATION j

BASES (Cont'd) i 3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION ,

i i

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each ,

j channel is completed within the time limit assumed in the safety analyses. t No credit was taken in the analyses for those channels with response times indicated as not applicable. )

t Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time -

i verification may be demonstrated by either (1) in place, onsite, or offsite test measurements or (2) utilizing replacement sensors with certified response times.

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4 WATERFORD - UNIT 3 B 3/4 3-la Amendment No.113 1

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4 NPF-38-174 ATTACHMENT B 5

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. TABLE 3.3-1 (Continued)

ACTION STATEMENTS

2. Pressurizer Pressure - Pressurizer Pressure - High High Local Power Density - High DNBR - Low

3. Containment Pressure - Containment Pressure - High (RPS) Hig5 Containment Pressure - High (ESF)

4. Steam Generator Steam Generator Pressuru - Low l Pressure - Low Steam Generator AP 1 and 2 (EFAS 1 and 2)

5. Steam Generator Level Steam Generator Level- Low Steam Generator Level- Hign Steam Generator AP (EFAS)

6. Core Protection Local Power Density - High Calculator DNBR - Low STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST. Subsequent STARTUP and/or POWER OPERATION may continue if one channelis restored to OPERABLE status and the provisions of ACTION 2 are satisfied.

ACTION 4 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

ACTION 5 - With the number of channels OPERABLE one less those required by the Minimum Channels OPERABLE requirement, STARTUP and/or POWER OPERATION may continue provided the reactor trip breakers of the inoperable channel are placed in the tripped condition within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

ACTION 6 - a. With one CEAC inoperable, operation may continue for up to 7 days Provided that at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , each CEA is verified to be within 7 inches (inc!cated position) of all other CEAs in its group.

b. With both CEACs inoperable, operation may continue provided that:

1. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the DNBR margin required by Specification 3.2.4b (COLSS in service) or 3.2.4d (COLSS out of service) is satisfied and the Reactor Power Cutback System is disabled, and WATERFORD - UNIT 3 3/4 3-6 AMENDMENT NO. 5

e , . .

TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CAllBRATION TEST IS REQUIRED

1. Manual Reactor Trip N.A. N.A. R and S/U(1) 1, 2, 3*, 4*, 5*

2. Linear Power Level- High S D(2,4),M(3,4), Q 1, 2 Q(4)

3. Logarithmic Power Level- High S R(4) Q and S/U(1) 2#,3,4,5

4. Pressurizer Pressure - High S R Q 1, 2

5. Pressurizer Pressure - Low S R Q 1, 2

6. Containment Pressure - High S R Q 1, 2

7. Steam Generator Pressure - Low S R Q 1, 2

8. Steam Generator Level- Low S R Q 1, 2

9. Local Power Density - High S D(2,4), R(4,5) Q, R(6) 1, 2

10. DNBR - Low S S(7),D(2,4), Q, R(6) 1, 2 M(8),R(4,5)

11. Steam Generator Level- High S R Q 1, 2

12. Reactor Protection System Logic N.A. N.A. Q (11) and S/U(1) 1, 2, 3*, 4*, 5* l WATERFORD - UNIT 3 3/4 3-10 AMENDMENT NO. 69

a .. .

TABLE 4.3-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CAllBRATION TEST IS REQUIRED

13. Reactor Trip Breakers N.A. N.A. Q(10)(11), S/U(1) 1, 2, 3*, 4*, 5* l

14. Core Protection Calculators S D(2,4),R(4,5) Q(9),R(6) 1, 2

15. CEA Calculators S R Q,R(6) 1, 2

16. Reactor Coolant Flow - Low S R Q 1, 2 WATERFORD - UNIT 3 3/4 3-11

o

TABLE 4.3-1 (Continued) j- .

TABLE NOTATIONS l *With the reactor trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

The d provisions of Specification 4.0.4 are not applicable when reducing reactorywer to less than i

10 of RATED THERMAL POWER from a reactor powerlevel greater than 10 :

! of RATED THERMAL POWER. Upon reducing power below 10": of RATED THERMAL POWER, a CHANNEL FUNCTIONAL TEST shall be performed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if not performed during the l previous 31 days. This Requirement does not apply with the reactor trip breakers open. j l

(1) . Each startup or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.

'(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included), above 15% of RATED

' THERMAL POWER: adjust the Linear Power Level signals and the CPC addressable constant multipliers to make the CPC AT power and CPC nuclear power calculations agree with the calorimetric calculation if absolute difference is greater than 2%. During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reachin0 each major test power plateau and prior to proceeding to the next major test power l plateau.

(3) Above 15% of RATED THERMAL POWER, verify that the linear power subchannel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators. 1 i

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION l (5)- ' After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection Calculators shall use these elements.

, (6) This CHANNEL FUNCTIONAL TEST shall include the injection of simulated process signals into the channel as close to the sensors as practicable to verify OPERABILITY ,

including alarm and/or trip functions. ;

(7) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coolant pump differential pressure instrumentation or by calorimetric calculations and if necessary, adjust the CPC addressable constant flow coefficients such that !

each CPC Indicated flow is less than or equal to the actual flow rate. The flow measurement uncertainty is included in the BERR1 term in the CPC and is equal to or greater than 4%.

l l

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WATERFORD - UNIT 3 3/4 3-12 l

l

TABLE 4.3-1 (Continued)

TABLE NOTATIONS (8) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate as Indicated by each CPC is less than or equal to the actual RCS total flow rate determined by calorimetric calculations.

(9) The quarterly CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERABLE CPC.

(10) At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage trip function and the shunt trip function.

(11) The quarterly CHANNEL FUNCTIONAL TEST and n the auarterly Reactor Protection System Logic CHANNEL FUNCTIONAL TEST shall be scheduled and performed such that the Reactor Trip Breakers (RTBs) are tested at least every 6 weeks to accommodate the appropriate vendor recommended interval for cyclina of each RTB.

WATEiu ORD - UNIT 3 3/4 3-12a l L

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR PROTECTIVE AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION The OPERABILITY of the Reactor Protective and Engineered Safety Features Actuation Systems instrumentation and bypasses ensures that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.

The redundancy design of the Control Element Assembly Calculators (CEAC) provides reactor protection in the event one or both CEACs become inoperable. If one CEAC is in test or inoperable, verification of CEA position is performed at least every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . If the second CEAC fails, the CPCs will use DNBR and LPD penalty factors to restrict reactor operation to some maximum fraction of RATED THERMAL POWER. If this maximum fraction is exceeded, a reactor trip will occur.

, The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The quarterly frequency for the channel functional fests for these systems comes from the analyses presented in topical report CEN-327: RPS/ESFAS Extended Test interval Evaluation, as supplemented.

Testing frequency and allowed outage time for the Reactor Trip Breakers (RTBs) is described and analyzed in CEN NPSD-951. The quarterly RTB channel functional test a.rjd the RPS channel functional test are scheduled and performed such that RTBs are verified OPERABLE at least every 6 weekslo accommodate the sooropriate vendor recommended interval for cyclina of each RTB.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.

Sensor response time verification may be demonstrated by either (1) in place, onsite, or offsite test measurements or (2) utilizing replacement sensors with certified response times.

WATERFORD UNIT 3 B 3/4 3 1 AMENDMENT N0.69

_ _ _ _ _ _ _ _ _ _ _

ML20116D012

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