ML20079C556
| ML20079C556 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/14/1991 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20079C555 | List: |
| References | |
| NUDOCS 9106240009 | |
| Download: ML20079C556 (2) | |
Text
{{#Wiki_filter:Unit 3 l PBAPS LIMlllNG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A Reactivity Limitations 4.3.A Reactivity limitations TContrd) -{ 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 ,0 5 x 5 array may be inoperable at it.t 4 operable control t.d st separ?te any 2 inu e able o. If this r Specification cannot oe met the reactor shall not be started, or if at power, the reactor shall be brought to a cold shutdown condition within 24 hours. B. Control Rods B. Control Rods 1. Each control rod shall be 1. The coupling integrity shall coupled to its drive or be verified for each withdrawn completely inserted and the control rod as follows: control rod directional control valves disarmed
- a. When a rod is withdrawn i electrically except as in the first time after each I
3.3.B.I.a. This requirement refueling outage or after does not apply in the refuel maintenance, observe discernible condition when the reactor response of the nuclear is vented. Two control instrumentatt:a and rod rod drives may be removed position ind cation for as long as Specification 3.3.A.1 the " full-in" and " full-out" is met, position, llowever, for initial rods when response is not
- a. For control rod 38-23 for discernible, subsequent the remainder of cycle 8 (to exercising of these rods after be completed before 10/30/91).
the reactor is above the Rod Worth Hinimizer low power setpoint If coupling cannot be shall be performed to verify accomplished, the uncoupled control instrumentation response, rod may be withdrawn when > 10% of rated thermal power
- b. When the rod is fully only if all the following withdrawn the first time conditions are satisfied:
after each refueling outage or after maintenance observe
- 1) no other uncoupled control that the drive does not go rod is withdrawr; to the overtravel position.
- 2) the uncoupled control rod may not be withdrawn past notch position 46.
-101-l 9106240009 910614 PDR ADOCK 05000273 o PDR I.-
Unit 3 PBAPS -.IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i .)t3.8 Control Rods (Cont'd.) 4.3.B Control Rods (Cont'd.) c. During each refueling outage and after control rod maintenance, observe that the drive does not go to the overtravel position. d. When repositioning the uncoupled control rod, per Specification 3.3.B.1.a the uncoupled control rod's position shall be verified to have followed the control rod drPee by neutron. instrumentation (LPRM or TIP). If the control blade cannot be verified to have followed the drive out to its final position, then the rod shall be completely inserted and the control rod directional control valves disarmed electrically.
- 2..The control rod drive housing 2.
The control rod drive housing . support system shall be in support system shall.be in- . place during reactor power spected after reassembly and operation or when the: reactor the results of the Inspection coolant' system-is pressurized recorded. -above atmospheric' pressure-with. fuel in the reactor vessel, unless all control rods are fully inserted and Specification 3.3.A.1 is met. L 3.a.-DELETED 3.a.. DELETED b.iThe Rod Worth Minimizer b.1. Prior to the start of -(RWM) low power setpoint control rod withdrawal is greater than or equal to towards criticality and 10% of rated power. Whenever prior to attaining the the reactor is in the startup Rod Worth Minimizer low or run modes with thermal power setpoint during rod power less than or equal to insertion at shutdown, the the Rod Worth Minimizer (RWM). Rod Worth Minimizer (RWM) low power setpoint the shall be demonstrated to Rod Worth Minimizer shall be be operable by the operable except as follows: following checks: L fl. With the RWM inoperable after-the-
- a. The RWM computer on first 12 control rods are fully line diagnostic test withdrawn, operation may-cont
- m' shall tua successfully L
provided.that control rod movcmen', performed. L and compliance with the prescribed L control rod pattern are verified
- b. Prior to the start by a second licensed operator.or of control rod withdrawal
-technically qualified member of the only, proper annunciation station technical staff.. of the selection error of at least one l out-of-sequence control rod in a fully inserted group shall be verified. -102- , -..}}