ML20024H265
| ML20024H265 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/24/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20024H264 | List: |
| References | |
| NUDOCS 9105310072 | |
| Download: ML20024H265 (1) | |
Text
___.
tJL. 91/09 e
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.1.2 Tt'e reactor coolant system pressure and reactor vessel metal temperature shall be determined to be to the right of the criticality lim't line of Figure 3.4.6.1-1 curve C within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality and at least once per 70 ainutes during system heatup.
4.4.6.1.3 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 70*F:
a.
In OPERATIONAL CONDITION 4 when reactor coolant system' temperature is:
n 1.
< 100'F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
to deterMne
~
cho.n6es in nonte. rial 2.
< 80'F, at least once per 30 minutes.
p ro p e c ti e r.,._
b.
Within 30 minutes prior to and at least once per 30 minutes during tensioning of-the reactor vessel head bolting studs.
4.4.6.1;4 The. reactor vessel material spe:imens shall be removed and examined
-es e fur.ctica ef tig,e end T!;C;= L POWER as required by 10 CFR 50, Appendix @o
- .;rd:n:: with the :chedule in Teble 4.4.G.'. 3-1.----
4.4.6.1.5 The pressure-temperature limit curves in Figure 3.4.6.1-1 are valid through 10 effective full power years (EFPY) and shall be re-evaluated prior to exceeding 10EFPY, 9105310072 910524 PDR ADOCK 05000416 P
PDR GRAND GULF-UNIT 1 3/4 4-20 Amendment No. 75,
.