Text

Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable
	ML20153D577
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Site:	Waterford
Issue date:	09/23/1998
From:	; ENTERGY OPERATIONS, INC.
To:	;
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	NUDOCS 9809250103
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n NPF-38-210 ATTACHMENT A EXISTING SPECIFICATIONS 1

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9809250103 990923 PDR ADOCK 05000382 P PDR

I TABLE 2.2-1 '

REACTOR PROTECTIVE INSTRUMENTAil0N TRIP SETPOINT LINITS t

FUNCTIONAL UNIT

,, TRIP SETPOINT ALLOWABLE VALUES .

i

1. Manual Reactor Trip Not Applicable Not Applicable -

2. Linear Power Level - High '

Four Reactor Coolant Pumps s 108% of RATED THERNAL POWER Operating S 108.76% of RATED THERMAL POWER l ,

3. Logarithmic Power level - High (1) s 0.257% of RATED THERNAL POWER S 0.280% of RATED THERNAL POWER

4. Pressurizer Pressure - High 5 2350 psia s 2359 psia !

5. Pressurizer Pressure - Low 2 1684 psia (2) 2 1649.7 psia (2)

6. Containment Pressure - High 5 17.1 psia s 17.4 psia

7. Steam Generator Pressure - Low 2 764 psia (3) 2 749.9 psia (3)

8. Steam Generator Level - Low 2 27.4% (4) 1 26.48% (4)

9. Local Power Density - High 5 21.0 kW/ft'(5) s 21.0 kW/ft (5) ;

10. DN8R - Low 2 1.26 (5) 2 1.26 (5) !

11. Steam Generator Level - High 5 87.7% (4) s 88.62% (4) !

l

12. Reactor Protection System logic Not Applicable Not Applicable :

13. Reactor Trip Breakers Not Applicable Not Applicable i

14. Core Protection Calculators Not Applicable Not Applicable '

15. CEA Calculators Not Applicable Not Applicable .

16. Reactor Coolant Flow - Low 2 19.00 psid (7) 2 18.47 psid (7) !

l '

t WATERFORD - UNIT 3 2-3 Amendment No. 12,113 I

_ 7 __ _ _ _ _ _ _ _ _

TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS JABLE NOTATIONS (1) Trip may be manually bypassed above 10 *% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10 *% of RATED THERMAL POWER.

(2) Value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased

! until the trip setpoint is reached. Trip may be manually bypassed below l

400 psia; bypass shall be automatically removed whenever pressurizer

} pressure is greater than or equal to 500 psia.

(3) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.

(4) % of the distance between steam generator upper and low level instrument nozzles.

! (5) As stored within the Core Protection Calculator (CPC). Calculation of the trip setpoint includes measurement, calculational and processor uncertainties, and dynamic allowances. Trip may be manually bypassed below 10 4% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10 *% of RATED THERMAL POWER. -

(6) Note 6 has been deleted.

(7) The setpoint may be altered to disable trip function during testing pursuant to Specification 3.10.3.

f i

WATERFORD - UNIT 3 2-4 AMENDMENT NO. 12

TABLE 3.3-1

d .

= REACTOR PROTECTIVE INSTRUMENTATION .

m S NINIMUN

~

i

. TOTAL NO. CHANNELS CHANNELS APPLICABLE -

I FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE MODES ACTION E

Z 1. Manual Reactor Trip 2 sets of 2 1 set of 2 2 -sets of 2 1 2 1 w !

4 2 sets of 2 1 set of 2 2 sets of 2 3A , 4* , 5* 8

2. Linear Power Level - High 4 2 3 1, 2 2#, 3#

3. Logarithmic Power Level-High

a. Startup and Operating 4 2(a)(d) 3 2** 2#, 3#

4 2 3 3*, 4*, 5* 8

b. Shutdown 4 0 2 3, 4, 5 4

4. Pressurizer Pressure - High 4 2 3 1, 2 2#, 3#

y 5. Pressurizer Pressure - Low 4 2(b) 3 1, 2 2#, 3#

w 6. Containment Pressure - High 4 2 3 1, 2 2#, 3#

7. Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

8. Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

9. Local Power Density - High 4 2(c)(d) 3 1, 2 2#, 3#

10. DISR - Low 4 2(c)(d) 3 1, 2 2#, 3# -

11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 3#

12. Reactor Protection System Logic 4 2 3 I 2 5 !'

m R 3g, 4*, 5* 8 ,

5 13. Reactor Trip Breakers 4 2(f) 4 1 2 5 iR 3;, 4* , 5* 8 E 14. Core Protection Calculators \

4 2(c)(d) 3 1, 2 2#, 3# and 7 i h 15. CEA Calculators 2 1 2(e) 1, 2 6 and 7 M 16. Reactor Coolant Flow - Low 4/SG 2/SG(c) 3/SG 1, 2 2#, 3#

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TABLE 3.3-1 (Continued)

\

TABLE NOTATION '

1

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

The provisions of Specification 3.0.4 are not applicable.

- Not applicable above 10'5 RATED THERMAL POWER.

(a) Trip may be manually bypassed above 10~5 of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10'5 of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be auto-matically removed whenever pressurizer pressure is greater than or equal to 500 psia.

(c) Trip may be manually bypassed below 10'5 of RATED THERMAL POWER; bypass to 10'5 of RATED THERMAL POWER.shall be automatically removed w During testing pursuant to Special Test Exception 3.10.3, trip may be manually bypassed below 5% of RATED THERMAL POWER; bypass dall be automatically removed when THERMAL POWER is greater than or equal to M of RATED THERMAL POWER. '

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

4 (e) See Special Test Exception 3.10.2.

(f) Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.

(i,) Hi? steam generator level trip may be manually bypassed in Modes 1 and 2, at 20% power and below.

ACTION STATEMENTS ACTION 1 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the protective system trip breakers.

ACTION 2 -

- With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or 4

tripped condition within I hour. If the inoperable channel is bypassed, th desirability of maintaining this channel in the i

bypassed condition shall be documented by the Plant Operations i

Review Committee in accordance with plant administrative procedures. The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUTDOWN.

WATERFORD - UNIT 3 3/4 3-4 AMENDMENT NO. % 44,109

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g TABLE 4.3-1 '

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8 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS .

8 c CHANNEL MODES FOR WHICH CHANNEL CHANNEL 3 FUNCTIONAL UNIT CHECK CALIBRATION FUNCTIONAL SURVEILLANCE TEST IS REQUIRED U 1. Manual Reactor Trip N.A. N.A. R and S/U(1) 1, 2, 3 * , 4 * , 5 *

2. Linear Power Level - High 5 D(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

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

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

6. Containment Pressure - iligh 5 R Q 1, 2 5 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 D(2,4), R(4,5) Q, R(6) 1, 2

10. DNBR - Low S S(7), 0(2,4), Q, R(6) 1, 2 M(8), R(4,5)

11. Steam Generator Level - High 5 R Q 1, 2 E 12. Reactor Protection System g Logic M.A. N.A. Q and S/U(1) 1, 2, 3 * , 4 * , 5*

-E .

~

. , I TABLE 4.3-1 (Continued)

TABLE NOTATIONS

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

The provisions of Specification 4.0.4 are not applicable when reducing reactor power to less than 10-4% of RATED THERMAL POWER from a reactor power level greater than 10-4% of RATED THERMAL POWER.

Upon reducing power below 10-4% 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 previous 31 days. 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):

a. Between 15% and 80% of RATED THERMAL POWER, compare the Linear l Power Level, the CPC at AT power, and CPC nuclear power signals to the calorimetric calculation.

If any signal is within -0.5% to +10% of the calorimetric calculation, then d2 B2.t calibrate except as required during initial power ascension following refueling.

If any signal is less than the calorimetric calculation by more than 0.5%, then adjust the affected signal (s) to within 0.0% to

+10.0% of the calorimetric caluclation. l If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal (s) to within 0.0%

to 10% of the calorimetric.

b. At or above 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC A T power, and CPC nuclear power. signals to the calorimetric calculation. If any signal differs from the calorimetric calculation by an absciute difference of more than 2%, then adjust the affected signal (s) to agree win the calorimetric calculation within -2% to +2%.

During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

(3) Above 15% of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore dete srs are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.

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

(5) After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine or verify acceptable values for the shape annealing matrix elements used in the Core Protection Calculators.

WATERFORD - UNIT 3 3/4 3-12 AMENDMENT NO. 69,125

\ .

BASES

, ,Hanual Reactor Trio l

l The Manual Reactor Trip is a redundant channel to the automatic l capability.instrumentation channels and provides manual reactor trip protective !

! l Linear Power Level - Hiah l

The Linsar Power Level - High trip provides reactor core protection i

against rapid reactivity excursions which might occur as the result of an ejected CEA. This trip initiates a reactor trip at a linear power level of less than or equal to 108% of RATED THERMAL POWER.

l Loaarithmic Power level - Hioh The Logarithmic Power Level - High trip is provided to protect the integrity of fuel cladding and the Reactor Coolant System pressure boundary in the event of an unplanned criticality from a shutdown condition. A reactor trip is initiated by the Logarithmic Power Level - High trip at a THERMAL i POWER level of less than or equal to 0.257% of RATED THERMAL POWER unless this trip is manually bypassed by the operator. The operator may manually bypass this trip when the THERMAL POWER level is above 10-4% of RATED THERMAL POWER; this bypass is automatically removed when the THERMAL POWER level decreases to 10-4% of RATED THERMAL POWER.

Pressurizer Pressure - Hiah l

The Pressurizer Pressure - High trip, in conjunction with the pressurizer safety valves and main steam safety valves, provides Reactor Coolant System protection against overpressurization in the event of loss of load without reactor trip. This trip's setpoint is at less than or equal to 2350 psia which is below the nominal lift setting of 2500 psia for the pressurizer safety valves and its operation avoids the undesirable operation of the pressurizer safety valves.

Pressurizer Pressure - Low l _

The Pressurizer Pressure - Low trip is provided to trip the reactor and to assist the Engineered Safety Features System in the event of a Loss of Coolant Accident. During normal operation, this trip's setpoint is set at greater than or equal to 1684 psia. nis trip's setpoint may be manually decreased, to a minimum value of 100 psia, as pressurizer pressure is reduced during plant shutdowns, provided the margin between the pressurizer pressure l and this trip's setpoint is maintained at less than or equal to 400 psi; this setpoint increases automatically as pressurizer pressure increases until the trip setpoint is reached.

WATERFORD - UNIT 3 B 2-3 Amendment No.113 t

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NPF-38-210 ATTACHMENT B PROPOSED SPECIFICATIONS 1

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE 2.2-1

~!*

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

1. Manual Reactor Trip Not Applicable Not Applicable i

2. Linear Power Level - High Four Reactor Coolant Pumps s 108% of RATED THERMAL POWER Operating S 108.76% of RATED THERMAL POWER l

3. Logarithmic Power Level - High (1) 5 0.257% of RATED THERMAL POWE 4.

s 0.280% of RATED THERNAL POWE ( )

Pressurizer Pressure - High 5 2350 psia 5 2359 psia

5. Pressurizer Pressure - Low 2 1684 psia (2) 2 1649.7 psia (2)

6. Containment Pressure - High 5 17.1 psia s 17.4 psia i

7. Steam Generator Pressure - Low 2 764 psia (3) 1 749.9 psia (3)

8. Steam Generator Level - Low 2 27.4% (4) 1 26.48% (4)

9. Local Power Density - High s 21.0 kW/ft (5)

, 5 21.0 kW/ft (5)

10. DNBR - Low 2 1.26 (5) i 2 1.26 (5) !

i

11. Steam Generator Level - High s 87.7% (4) s 88.62% (4) l

12. Reactor Protection System logic Not Applicable Not Applicable

13. Reactor Trip Breakers Not Applicable Not Applicable

14. Core Protection Calculators Not Applicable Not Applicable 152 CEA Calculators Not Applicable Not Applicable i

16. Reactor Coolant Flow - Low 2 19.00 psid (7) 2 18.47 psid (7) l i

I WATERFORD - UNIT 3 2-3 Amendment No. 12,113 [

TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS gger / TABLE NOTATIONS

. (1) Tr may be manually bypasse above 10 *% of RATED THERMAL WER; bypass) 11 be automatically rem ed when THERMAL POWER is les

/ o 10 *% of RATED THERMA. OWER. f thanorequaji l

(2) Value may be decreased manually, to a minimum of 100 psia, as pressurizer l

! pressure is reduced, provided the margin between the pressurizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 500 psia.

(3) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.

(4) % of the distance between steam generator upper and low level instrument l nozzles.

(5) As stored withi e Core Projet culato (CPC). Calculation of i

I the trip set nt include asureme , calculational and processor uncertain 'es, and dyn c allowan s. Trip may be manually bypassed below 1 *% of RATE HERMAL POWER, bypass shall be automatically removed when ydRMAL POWE is greater than or equal to 10 *% of RATED THERMAL

, POWERr, .

N (6)(No)(6hp(beende4eted.1 (7) The setpoint may be altered to disable trip function during testing pursuant to Specification 3.10.3. i l

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A LvQ WATERFORD - UNIT 3 2-4 AMEN 0 MENT NO. 12

l INSERT 1 (1) Trip may be manually bypassed above 10-4% of RATED THERMAL POWER *;

bypass shall be automatically removed when THERMAL POWER' is less than or !

i' equal to the reset point of the bistable. The reset point shall be within 3.0x10-5%

! of RATED THERMAL POWER

below the bistable setpoint which is nominally 10-4% of RATED THERMAL POWER *. This accounts for the deadband of the bistable.

l 1

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TABLE 3.3-1 Ei A'

REACTOR PROTECTIVE INSTRUMENTATION m y E MINIMUM ts %

FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS CHANNELS TO TRIP CHANNELS OPERABLE APPLICABLE MODES ACTION .

$2!

=

Q 1. Manual Reactor Trip 2 sets of 2 1 set of 2 2. sets of 2 1 2 93 1

w 2 sets of 2 1 set of 2 2 sets of 2 3 I, 4*, 5* 4 ;

2. Linear Power Level - High 4 2 3 1, 2 8 il! ;I 2#, 3# $1

3. Logarithmic Power Level-High

a. Startup and Operating b 4 2(a)(d) 3 2** 2#, 3# $

4 2 3 3* , 4* , 5* 8

b. Shutdown 4 0 2 3, 4, 5 4

4. Pressurizer Pressure - High 4 2 3 1, 2 2#, 3#

5. Pressurizer Pressure - Low

$ 4 2(b) 3 1, 2 2#, 3#

w 6. Containment Pressure - High 4 2 3 1, 2 2#, 3#

7. Steam Generator Pressure - Low 4/SG 2/SG 1, 2 3/SG 2#, 3#

8. Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

9. Local Power Density - High 4 2(c)(d) 3 1, 2 2#, 3#

10. DER - Low 4 2(c)(d) 3 1, 2 2#, 3#

11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 3#

12. Reactor Protection System Logic 4 2 3 1 2 5 R

m 3I , 4* , 5* 8

13. Reactor Trip Breakers 4 2(f) 4 1 2 5 k I 4*,

3 , 5* 8 N 14. Core Protection Calculators 4 2(c)(d) 3 1, 2 2#, 3# and 7 .

! 15. CEA Calculators 2 1 2(e) 1, 2 6 and 7

,M 16. Reactor Coolant Flow - Low 4/SG 2/SG(c) 3/SG 1, 2 2#, 3# l

TABLE 3.3-1 (Continued)

TABLE NOTATION

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

The provisions of Specification 3.0.4 are not applicable.

**Not applicable above 10'S RATED THERMAL POWE i

(a) Trip ay be manually bypa ed above 10'5 of RATED HERMAL POWER; b ass I

! 1 be automatically moved when THERMAL 4

( sh 5 of RATED THERMA _

ER.

is less than o ual to !

(b) Trip may be manually bypassed below 400 psia bypass shall be auto-matica11y to 500 psia. removed whenever pressurizer pressu;re is greater than or eq g i (c) Trip may be manually bypassed bel 10'S of RATED THERMAL i shall be automatically removed ; bypass en THERMAL POWE is greater than or equal to 10'5 of RATED THERMAL POWER. During testing pursuant to Special Test l 1

i Exception 3.10.3, trip may be manually bypassed below 5% of RATED THERMAL ;

! POWER; bypass shall be automatically removed when THERMAL POWER is greater !

', than or equal to 5% of RATED THERMAL POWER. '

4 j (d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e) See Special Test Exception 3.10.2. I 2

(f) Each channel shall be comprised of two trip breakers; actual trip logic 3

1 shall be one-out-of-two taken twice.

^

i (g)

' High steam generator level trip ma; ue manually bypassed in Modes 1 and 2, at 20% power and below.

ACTION STATEMENTS ACTION 1 -

With the number of. channels OPERABLE one less than required by the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/o't open the protective system trip breakers.

ACTION 2 -

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within I hour. If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be documented by the Plant Operations Review Committee in accordance with plant administrative procedures. The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUTDOWN.

WATERFORD - UNIT 3 4 3-4 AMENDMENT NO. 44r40,109 O) th meas nel L7 S A')"'Y" ? "

l' l

INSERT 2 (a) Trip may be manually bypassed above 104% of RATED THERMAL POWER (1);

bypass shall be automatically removed when THERMAL POWER (1) is less than or l equal to the reset point of the bistable. The reset point shall be within 3.0x10-5% I of RATED THERMAL POWER (1) below the bistable setpoint which is nominally 104% of RATED THERMAL POWER (1). This accounts for the deadband of the I bistable.

i l

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7 TABLE 4.3-1 3

g k6 e

o REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS $

g*

b; CHANNEL MODES FOR WHICH E FUNCTIONAL UNIT CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE D a CHECK CALIBRATION w

TEST IS REQUIRED 9'

1. Manual Reactor Trip N.A.

2.

N.A. R and S/U(1) 1,2,3*,4*,5*f'MC Linear Power Level - High 5 0(2,4),M(3,4), Q L '

1, 2 -

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

4. Pressurizer Pressure - High 5 R Q 1, 2

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

[ 6. Containment Pressure - High 5 R Q 1, 2 o 7. Steam Generator Pressure - Low 5 R Q 1, 2 '

8. Steam Generator Level - Low 5 R Q 1, 2 r

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

10. DNBR - Low 5 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 E 12. Reactor Protection System j Logic N.A. N.A.

i Q and S/U(1) 1, 2, 3*, 4*, 5*

'i 5

D

\

TABLE 4.3-1 (Continued) I l, TABLE NOTATIONS CO j

~ *Wita the reactor trip breakers in the closed position, thh CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

' #The provisions of Specification 4.0.4 are not applicable hen

reducing reactor power to less than 10-4% of RATED THE L POWER from a reactor power level greater than 10-4% of RATED THE L POWE .

1 i

Upon reducing power below 10-4% of RATED THERMAL POWE , 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 l l during the previous 31 days. This requirement does not apply with d

the reactor trip breakers open.

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

{ (2) Heat balance only (CHANNEL FUNCTIONAL TEST not included):

a. Between 15% and 80% of RATED THERMAL POWER, compare the Linear I l

Power Level, the CPC at AT power, and CPC nuclear power signals l to the calorimetric calculation.

i

If any signal is within -0.5% to +10% of the calorimetric calculation, then d2 n9.t calibrate except as required during initial power ascension following refueling.

1 If any signal is less than the calorimetric calculation by more

! than 0.5%, then adjust the affected signal (s) to within 0.0% to j +10.0% of the calorimetric caluclation.

! If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal (s) to within 0.0%

i to 10% of the calorimetric.

t- b. At or above 80% of RATED THERMAL POWER, compare the Linear Power j Level, the CPC A T power, and CPC nuclear power. signals to the l l calorimetric calculation. If any signal differs from the !

I calorimetric calculation by an absolute difference of more than i 2%, then adjust the affected signal (s) to agree with the j calorimetric calculation within -2% to +2%.

! During PHYSICS TESTS, these daily calibrations may be suspended i provided these calibrations are performed upon reaching each major i test power plateau and prior to proceeding to the next major test i power plateau.

! (3) Above 15% of RATED THERMAL POWER, verify that the linear power sub-

! channel gains of the excore detectors are consistent with the values

used to establish the shape annealing matrix elements in the Core Protection Calculators.

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

j (5) After each fuel loading and prior to exceeding 70% of RATED THERMAL i POWER, the incore detectors shall be used to determine or verify

{ acceptable values for the shape annealing matrix elements used in the j Core Protection Calculators.

WAT RFORD - UNIT 3 3/4 3-12 AMENDMENT NO. 69,125

i BASES

'Ma'nual Reactor Trio The Manual Reactor Trip is a redundant channel to the automatic capability.instrumentation channels and provides manual reactor trip protective l Linear Power Level - Hiah l

The Linear Power Level - High trip provides reactor core protection against ejected CEA.

rapid reactivity excursions which might occur as the result of an This trip initiates a reactor trip at a linear power level of less than or equal to 108% of RATED THERMAL POWER.

l I

Loaarithmic Power level - Hiah The Logaritiaic Power Level - High trio is provided to protect the

! integrity of fuel s.1 adding and the Reactor Coolant System pressure boundary in the event of an unpitnned criticality from a shutdown condition. A reactor trip is initiated by the Logarithmic Power Level - High trip at a THERMAL l POWE level of less than or equal to 0.257% of RATED THERMAL POWERWnless this

! trip manually bypassed by the operator. . The operator may manua' ly bypass i this t p when the THERMAL POWER evel is above 10-4% of RATED THE MAL POWE.

i thisbyqssisautomaticallyremo hen the THERMAL POWE level Jecreases to l 10-4% of TED THERMAL POWER ( .

l .. - - = -

Pressurizer Pressure - Hiah 4 _

The Pressurizer Pressure - High trip, in conjunction with the pressurizer safety valves and main steam safety valves, provides Reactor Coolant System protection against overpressurization in the event of loss of load without reactor trip. This trip's setpoint is at less than or equal to 2350 psia which is below the nominal lift setting of 2500 psia for the pressurizer i

safety valves and its operation avoids the undesirable operation of the l pressurizer safety valves. ;

Pressurizer Pressure - Low The Pressurizer Pressure - Low trip is orovided to trip the rszctor and to assist the Engineered Safety Features Systee in tne event of a loss of Coolant Accident. During normal operation, this trip's setpoint is set at greater than or equal to 1684 psia. This trip's setpoint may be manually decreased, to a minimum value of 100 psia, as pressurizer pressure is reduced i

I during plant shutdowns, provided the margin between the pressurizer pressure and this trip's setpoint is maintained at less than or equal to 400 psi; this setpoint increases automatically as pressurizer pressure increases until i the trip setpoint is reached.

WATERFORD - UNIT 3 B 2-3 Amendment No.113

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ML20153D577

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