ML20029A322
| ML20029A322 | |
| Person / Time | |
|---|---|
| Site: | Callaway  (NPF-30-A-058, NPF-30-A-58) |
| Issue date: | 01/31/1991 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20029A323 | List: |
| References | |
| NUDOCS 9102180202 | |
| Download: ML20029A322 (2) | |
Text
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REACTIVITY CON; O LSYSTEMS SHUTDOWN ".00 a.JUN LIMIT L1MITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be limited in physical insertion as specified in the Core Operating Limits Report (COLR).
APPLICABILITY: MODES 1* and 2*#.
ACTION:
With a maximum of one shutdown rod inserted beyond the insertion limit specified ir. the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:
a.
Restore the rod to within the insertion limit specified in the COLR, or b.
Declare the rod to be inoperable and apply Specification 3.1.3.1.
SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be detennined to be within the insertion limit specified in the COLR:
a.
Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or D during an-approach to reactor criticality,
~and b.
At least once-per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereaf ter.
S'ee Special Test Exceptions Specifications 3.10.2 and 3.10.3.
- With_Keff greater than or equal to 1.
1 CALLAWAY - UNIT 1 3/4 1-20 Amendment No. 29,58 9th2180202 9101317 PDR ADOCK 05000483 P
PDfD
i
)
4 lREACTfVITY CONTROL SYSTEMS
_ ROD DROP TIME t
LIMITING CONDITION FOR-OPERATION 1
r 3.1.3.4 The individual full-length shutdown and control rod drop time from the fully withdrawn position shall be less than or equal to 2.7 seconds from l
beginning of decay of stationary gripper coil voltage to dashpot entry with:
T,yg greater than or equal to 551*F, and a.
b.
All Reactor Coolant pumps operating.
- APPLICABILITYi.- H0 DES 1 and.2.
ACTION:
[
a.
With the rod drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit-prior to proceeding to MODE 1 or 2.
b.
With the rod drop times within limits-but determined with three reactor coolant-pumps operating, operation may proceed provided THERMAL POWER is restrictad to less than or equal to 66% of RATED
-THERMAL POWER.
" SURVEILLANCE REQUIREMENTS
=4.1.3.4 The rod drop time of_ full-length rods shall be demonstrated through measurement prior to reactor criticality:
For all rods following each' removal of the reactor vessel head,
{
a.
b.
.For specifically affected individual' rods following any maintenance on or modification to the Control-Rod Drive System which could affect thel drop-time of those specific rods, and c.
At least once per 18 months, i
l 1
CALLNWAY-UNIT 1-3/4 1-19 Amendment No. JE,28 l
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