ML20058A951
| ML20058A951 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/22/1993 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20058A926 | List: |
| References | |
| NUDOCS 9312010328 | |
| Download: ML20058A951 (2) | |
Text
.
.. =.
3 ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION j
UNIT 3 l
Docket Nos. 50-278 License Nos. DPR-56 TECHNICAL SPECIFICATION CHANGES
[
t List of Attached Pages Unit 3 101 I
r I
i P
I t
i 1
i 4
l t
i 4
4 I
I 9312010328 931122
.PDR ADOCK 05000278 P
_ _ ~
Unit 3 PBAPS 4
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity Limitations 4.3.A Reactivity Limitationt (Cont'd)
(Cont'd) f.
Inoperable control rods shall be positioned such that specification 3.3.A.1 is met.
In addition, during reactor power operation, no more than one control rod in any 5 x 5 array may be operable (at least 4 operable control rods must separate any 2 inoperable ones).
If this Specification cannot be met the reactor shall not be started, or if at power, the reactor shall be brought to a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Control Rods 1.
Each control rod shall be B. Control Rods coupled to its drive or completely inserted and the
- 1. The coupling integrity shall control rod directional be verified for each withdrawn control valves disarmed control rod as follows:
electrically except as in 3.3.B.I.a.
This requirement
- a. When a rod is withdrawn does not apply in the refuel the first time after each condition when the reactor refueling outage or after is vented.
Two control maintenance, observe discernible rod drives may be removed response of the nuclear ac long as Specification 3.3.A.1 instrumentation and rod is met, position indication for the " full-in" and " full-out"
- a. For contral rod 54-35, for position.
However, for initial the remainder of cycle 10 (to rods when response is not i
be completed before 10/30/95).
discernible, subsequent exercising of these rods after If coupling cannot be the reactor is above the Rod Worth accomplished, the uncoupled control Minimizer low power setpoint rod may be withdrawn unen 210%
shall be performed to verify of rated thermal power instrumentation response.
only if all the following conditions are satisfied:
- b. When the rod is fully withdrawn the first time
- 1) no other uncoupled control after each refueling outage rod is withdrawn; or after maintenance observe that the drive does not go
- 2) the uncoupled control rod to the overtravel position.
may not be withdrawn past notch position 46.
-101-t E
r e
e