ML20153B444
| ML20153B444 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/18/1998 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20153B441 | List: |
| References | |
| NUDOCS 9809230122 | |
| Download: ML20153B444 (12) | |
Text
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NPF-38-210 J
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ATTACHMENT A EXISTING SPECIFICATIONS 1
I 9009230122 993918 ~
PDR ADOCK 05000382 P
lABLE 2.2-1 REACTOR PROTECilVE INSTRUMENTAil0N TRIP SEIPOINT LINITS
't FUNCTIONAL UNIT TRIP SETPOINT_
ALLOWA8LE VALUES l.
Manual Reactor Trip Not Applicable Not Applicable s
2.
Linear Power Level - High r
Four Reactor Coglant Pumps s 108% of RATED THERMAL POWER S 108.76% of RATED THERMAL POWER Operating e
3.
Logarithmic Power' Level - High (1) 5 0.257% of RATED THERMAL POWER s 0.280% of RATED THERMAL POWER 4.
Pressurizer Pressure - High 5 2350 psia 5 2359 psia 5.
Pressurizer Pressure - Low 2 1684 psia (2) 2 1649.7 psia (2) i 6.
Containment Pressure - High s 17.1 psia s 17.4 psfn i
7.
Steam Generator Pressure - Low 2 764 psia (3) 2 749.9 psia (3) 8.
Steam Generator Level - Low 1 27.4% (4) 2 26.48% (4)
[
9.
Local Power Density - High 5 21.0 kW/ft (5)
$ 21.0 kW/ft (5)
- 10. DNBR - Low 2 1.26 (5) 2 1.26 (5)
- 11. Steam Generator Level - High 5 87.7% (4) 5 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 r
- 15. CEA Calculators Not Applicable Not Applicable
[
16.
Reactor Coolant Flow - Low 2 19.00 psid (7) 2 18.47 psid (1) l i
1 i
h WATERFORD - UNIT 3 2-3 Amemiment No. 17,111
i TABLE 2.2-1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS
{
i TABLE 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 r
$1 to 400 psi; the setpoint shall be increased automatically as pressurizt assure is increased until the trip setpoint is reached.
Trip may anually bypassed below a
400 psia; bypass shall be automatically removeu *nenever 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 j
is maintained at less than or equal to 200 psi; the setpoint shall be increased automatically as steam generator pressure is increased until i
the trip setpoint is reached.
l (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 *% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10 4% of RATED THERMAL POWER.
I (6'
Note 6 has been deleted.
(7) The setpoint may be altered to disable trip function during testing pursuant to Specification 3.10.3.
3_
WATERFORD - UNIT 3 2-4 AMENDMENT NO. 12
'i o
I 1ABLE 3.3-1 EM REACIOR PROTECTIVE INSTRUMENTATION as S
E NININUN FUNCTIONAL UNIT TOTAL NO.
CHANNELS CHANNELS APPLICABLE OF CHANNELS 10 TRIP OPERABLE MODES ACTION E
Q 1.
Manual Reactor Trip *i 2 sets of 2 1 set of 2 2 sets of 2 1 2 1
A 2 sets of 2 1 set of 2 2 sets of 2 3, 4*, 5*
8 w
2.
Linear Power Level - liigh 4
2 3
1, 2 2#, 3#
3.
Logarithmic Power Level-High a.
Startup and Operating 4
2(a)(d) 3 2**
2#, 3#
1 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#
2:*
5.
Pressurizer Pressure - Lou 4
2(b) 3 1, 2 2#, 3#
+
6.
Containment Pressure - High 4
2 3
1, 2 2#, 3#
w 7.
Steam Generator Pressure - Lou 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 - Lou 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
R 3g, 4*, 5*
8
- 13. Reactor Trip Breakers 4
2(f) 4 I 2 5
k 3g, 4*, 5*
8
}
N
- 14. Core Protection Calculators 4
2(c)(d) 3 1, 2 2#, 3# and 7 h
- 15. CEA Calculators 2
1 2(e) 1, 2 6 and I
,M
- 16. Reactor Coolant Flow - Low 4/SG 2/SG(c) 3/SG 1, 2 2#, 3#
l e
4 l
1.
TABLE 3.3-1 (Continued) d 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.
4
- The provisions of Specification 3.0.4 are not applicable.
- Not applicable above 10'S RATED THERMAL POWER.
(a)
Trip may be manually bypassed above 10'5 of RATED THERMAL POWER; byp 10'5 of RATED THERMAL POWER.shall be automatically removed w (b) Trip may be manually bypassed below 400 psia; bypass shall be auto-matica11y removed whenever pressurizer pressure is greater than or equal to 500 psia.
i (c)
Trip may be manually bypassed below 10'S of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10'5 of RATED THERMAL POWER.
During testing pursuant to Special Test Exception 3.10.3, trip may be manually bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERNAL POWER is greater than or equal to 5% of RATED THERMAL POWER.
(d) Trip may be bypassed during testing pursuant to Special Test Exception j
3.10.3.
(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.
(g) High 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 OPERA 8LE one less than required by the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in n,
at least NOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the protective system trip breakers.
ACTION 2.
With the number of channels 0PERA8LE 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 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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 OPERA 8LE status prior to STARTUP following the next COLD SHUTDOWN.
WATERFORD - UNIT 3 3/4 3-4 AMENDMENT N0. 44 40,109 7
aA_,e A
A
+, _ - -
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-et k
e NPF-38-210 ATTACHMENT B PROPOSED SPECIFICATIONS 4
TA8LE 2.2-1 REACTOR PROTECTIVE INSTRUMENIAll0N TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINI ALLOWABLE VALUES 1.
Manual Reactor Trip Not Applicable Not Applicable 2.
Linear Power Level - High i
Four Reactor Co9 ant Pumps 5108% of RATED THERMAL POWER
$ 108.76% of RATED THERMAL POWER l[
1 Operating
.e i
3.
Logarithmic Power' Level - High (1) s 0.257% of RAi[D 1HERMAL POWER 5 0.280% of RATED THERMAL POWER 4.
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 7.
Steam Generator Pressure - Low 2 764 psia (3) 2 749.9 psia (3)
)h o g 8.
Steam Generator Level - Low 2 27.4% (4) 2 26.48% (4) n A >,
9.
Local Power Density - High 5 21.0 kW/ft (5) 5 21.0 kW/ft (5)
(2
- 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 2
a-
- 13. Reactor Trip Breakers Not Applicable Not Applicable I
s E. %
- 14. Core Protection Calculators Not Applicable Not Applicable i0 W
- 15. CEA Calculators Not Applicable Not Applicable 16.
Reactor Coolant flow - Low 2 19.00 psid (7) 2 18.47 psid (1) l WATERFORD - UNIT 3 2-3 Amemiment No. 17. I l I
i* -
l TABLE 2.2 _1 (Continued)
REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS IABLE NOTATIONS all em e w E
P i
l (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 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 t
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 *% 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.
4 4
l L
l l
4 WATERFORD - UNIT 3 2-4 AMENDMENT NO. 12
_ = _ _.
INSERT 1 (1)
Trip may be manually bypassed above 104% 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 104% of RATED THERMAL POWER. This accounts for the deadband of the bistable.
+
l 4
.~
IABLE 3.3-1
~
gQ3 2-T t
y REACTOR PROTECTIVE INSTRUMENTATION
}
i MINIMUM
['
TOTAL NO.
CHANNELS CHANNELS APPLICABLE 2
FLAICT10NAL UNIT OF CHANNEL 5 10 TRIP OPERA 8tE MODES ACT10N 4
t h
"T Q
l.
Blanual Reactor Trip #i 2 sets of 2 1 set of 2 2 sets of 2 1 2 1
R A
2 sets of 2 1 set of 2 2 sets of 2 3, 4*, 5*
8 w
2.
Lirear Power Level - W gh 4
2 3
1, 2 2#, 3#
I h.
3.
Logarithmic Power Level-High
^
f )
a.
Starte,and Operating 4
2(a)(d) 3 2**
2#, 3#
I 4
2 3
3*, 4*, 5*
8 y
g b.
Shutdown 4
0 2
3, 4, 5 4
a f
4.
Pressurizer Pressure - High 4
2 3
1, 2 2#, 3#
l 3
5.
Pressurizer Pressure - Lou 4
2(b) 3 1, 2 2#, 3#
j w
6.
Containment Pressure - High 4
2 3
1, 2 2#, 3#
7.
Steam Generator Pressure - Lou 4/SG 2/SG 3/SG 1, 2 2#, 3#
8.
Steam Generator Level - Lou 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 - Lou 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
R 3g, 4*, $*
8 m*
- 13. Reactor Trip Breakers 4
2(f) 4 I 2 5
k g
3, 4 *, 5" 8
E
- 14. Core Protection Calculators 4
2(c)(d) 3 1, 2 2#, 3# and 1 k
- 15. CEA Calculators 2
1 2(e) 1, 2 6 and /
i
,M
- 16. Reactor Coolant Flow - Low 4/SG 2/SG(c) 3/SG 1, 2 2#, 3#
l
=
4,Ek
i TABLE 3.3-1 (Continuedl TABLE NOTATION 6
' 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 POWER.
caI r
a1 e
os ho ved T RMAL R
1 10' of TED HE L
ER.
(b) Trip may be manually bypassed below 400 psia; bypass shall be auto-matica11y removed whenever pressurizer pressure is greater than or equal to 500 psia.
(c) Trip may be manually bypassed below 10'S of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10'5 of RATED THERMAL POWER.
During testing pursuant to Special Test 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.
(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.
(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.
)
(g)
High steam generator level trip may be manually bypassed in Modes 1 and 2 at 20% power and below.
i ACTION STATEMENTS ACTION 1 With the number of channels OPERA 8LE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in
- s at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the protective system trip breakers.
ACTION 2.
With the number of channels OPERA 8LE 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 3/4 3-4 AMEN 0 MENT NO. Mr40,109
j INSERT 2 4
(a)
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 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.
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