ML20029D447
| ML20029D447 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/27/1994 |
| From: | AFFILIATION NOT ASSIGNED |
| To: | |
| Shared Package | |
| ML20029D438 | List: |
| References | |
| NUDOCS 9405050398 | |
| Download: ML20029D447 (3) | |
Text
_ __
i a
e 1
i a
5 l
1 1
]
ATTACHMENT 2 i
LIMERICK GENERATING STATION i
UNITS 1 AND 2 Docket Nos.
50-352 1
50-353 i
l License Nos.
NPF-39 i
NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST No. 94-14-0 4
I LIST OF AFFECTED PAGES 4
Unit 1 UnN2 i
^
3/44-2 3/44-2 1
4 9405050398 940427 PDR ADDCK 05000352 P
PDR y-*
v-eMw w
~
' REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS 4.4.1.1.1 DELETED l
4.4.1.1.2 Ear.h pump MG set scoop tube mechanical and electrical stop shall be demonstrated OPERABLE with overspeed setpoints less than or equal to 109% and 107%, respectively, of rated core flow, at least once per 18 months.
4.4.1.1.3 Establish a baseline APRM and LPRM** neutron flux noise value within the regions for which monitoring is required (Specification 3.4.1.1, ACTION c) within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for which monitoring is required unless baselining has previously been performed in the region since the last refueling outage.
4.4.1.1.4 With one reactor coolant system recirculation loop not in operation, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that:
a.
Reactor THERMAL POWER is s 70% of RATED THERMAL POWER, b.
The recirculation flow control system is in the Local Manual mode, and c.
The speed of the operating recirculation pump is s 90% of rated pump speed.
d.
Core flow is greater than 39% when THERMAL POWER is within the restricted zone of Figure 3.4.1.1-1.
4.4.1.1.5 With one reactor coolant system recirculation loop not in operation, within 15 minutes prior to either THERMAL POWER increase or recirculation loop flow increase, verify that the following differential temperature requirements are met if THERMAL POWER is s 30% of RATED THERMAL POWER or the recirculation loop flow in the operating recirculation loop is s 50% of rated loop flow.
a.
s 145 F between reactor vessel steam space coolant and bottom head drain line coolant, b.
s 50*F between the reactor coolant within the loop not in operation and the coolant in the reactor pressure vessel, and c.
5 50*F between the reactor coolant within the loop not in operation and the operating loop.
The differential temperature requirements of Specification 4.4.1.1.5b. and c.
do not apply when the loop not in operation is isolated from the reactor pressure vessel.
LIMERICK - UNIT 2 3/4 4-2
i
- RIACTOR COOLANT SYSTEM-SURVEILLANCE REQUIREMENTS l
4.4.1.1.1 DELETED l
4.4.1.1.2 Each pump MG set scoop tube mechanical and electrical stop shall be l
' demonstrated OPERABLE with overspeed setpoints less than or equal to 109% and B
107%, respectively, of rated core flow, at least once per 18 months.
4.4.1.1.3.
Establish a baseline APRM and LPRM** neutron' flux noise value within i
the regions for which monitoring is required (Specification 3.4.1.1,' ACTION c)
L within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering the region for which monitoring is required unless baselining has previously been performed in the region since the last refueling j
outage.
4.4.1.1.4 With one reactor coolant system recirculation loop not in operation, at least. once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. verify that:
I a.
Reactor THERMAL POWER is s 70% of RATED THERMAL POWER, I
b.
The recirculation flow control system is in.the Local. Manual mode, and if c.
The speed of the operating recirculation pump is s'90% of rated pump
~
speed.
d.
Core flow is greater than 39% when THERMAL POWER is within the-l restricted zone of Figure 3.4.1.1-1.
1 4.4.1.1.5 With one reactor coolant system recirculation loop not in operation, within 15 minutes prior to either THERMAL POWER increase or recirculation loop flow increase, verify that the following differential temperature requirements j
are met if THERMAL POWER is s 30% of RATED THERMAL POWER or the recirculation j
loop flow in the operating recirculation. loop is s 50% of rated loop flow.
a.
s 145 F between reactor vessel steam space coolant and. bottom head drain line coolant, 4
b.
s 50*F between' the reactor coolant within the loop not,in operation j
and the coolant in the reactor pressure vessel,-and l
c.
s 50*F between the' reactor coolant within the loop not in operation l
and the operating loop.-
s
_i.
The differential temperature. requirements of Specification 4.4.1.1.5b. and c.
do not apply when the loop not in operation is isolated'from the reactor i
pressure vessel.
i 1
LIMFRICK - UNIT 1 3/4 4-2 i
)
.