ML20128L492
| ML20128L492 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/05/1993 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20128L472 | List: |
| References | |
| NUDOCS 9302190269 | |
| Download: ML20128L492 (3) | |
Text
,
^
.. Q '
o
-5 P
'(
ATTACHMENT II Technical Specification 2.1.1 Mark-up and.
Table 8-1 of-the Reload Report w
i L
i l
1 p
t-
.9302190269'930205 t
PDR 1ADOCK 05000413
' P;
- PDR-.
~
d r;
J2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS f
4 2.1 SAFETY LIMITS REACTOR CORE
]
2.1.1 The combinatiqs.-of1HE,Rbj%L_ POW pressurizer pressure, and the highest
-operatinglooy/foolanttemperature(T hall:not exceed the limits'shown in avg Figure 2.1rl' (" nit 1)-ana 2.1-1L-(Unit-19-f r four loop operation.
[-
APPLICABILITY:
FO ad c.
ACTION:
Whenever the point defined by the combination of the highest operating: loop average temper ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STAN0BY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and comply with the require-ments of Specification 6. 7.1.
REACTOR COOLANT SYSTEM PRESSURE 2.1.2-The Reactor Coolant System pressure shall not exceed 2735 psig.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTION:
NODES 1 and 2:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its-limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and comply with the requirements of Specification 6.7.1.
MODES 3, 4, and 5:
-Whenever the Reactor Coolant Syritem pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within~
- 5. minutes, and comply-with the requirements of Specification 6.7.1.
4 4
4 CATAWBA - UNITS 1 & 2 2-1 hendment No. 85 (41aM-13--
F 4 a.
Amendeent-Ho. * ' (UrtH. 2}-
r-e e
~.
u, s-s -.
+
l a
p
--]
4
- 1 4
l Table-B-1 Technical Specifiestion'Changesh Soecification Dencrintion of Chanae i
1 2.1.]
increased FAH for Mark-BW fuel changed CHF correlation.
~385,000 gpm reduced RCS minimum flow to q
s 2.2.1 increased Fag for Mark-BW fuel removed power range neutron' flux negative rate reactor' trip 1
3/4.2.1 deleted baseload operation 3/4.2.2 changed Fn methodology to reflect Duke nomenclatere l
quantified surveillance requirements-3/4.2.3 changed FAH methodology to reflect Duke nomenclature
-quantified surveillance requirements increased the tilt ratio at which power reduction-is 3/4.2.4 required incorporated RCS flow as DNB parameter.
3 '* ' 2 ' '
deleted Figure 8,
'RCS Flow vs. R-Four Loops in-E operation" trom COLR and remove unit specification ~from Technical Specification Figure 3,2-1.
0 reduced RCS minimum measured flow to' 385.000 gpm 3/4.3.1
'emoved power range neutron flux negative rate reactor-trip p.
3/4.3.2 increased low steam line pressure setpoints l-increased feedwater isolation response time 4
y increased steam line isolation response time.
l-removed steam--line pressure dynamic-compensation p
decreased Reactor Makeup Water Pump flowrate limit from' J
3/4.3.3.12 75 gpm to 70 gpm in Mode 5 l.
3/4.4.2.1 increased pressuri::er'. safety valve -lif t setpoint tolerance l'
8-3
{.
i:
l-7 nw
~,.
~
.