ML18106A429
| ML18106A429 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/26/1998 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18106A428 | List: |
| References | |
| NUDOCS 9804070142 | |
| Download: ML18106A429 (2) | |
Text
Document Control Desk LR-N980125 LCR S97-24 SALEM GENERATING STATION UNIT NO. 1 FACILITY OPERATING LICENSE DPR-70 DOCKET NO. 50-272 CHANGE TO TECHNICAL SPECIFICATIONS MOVABLE CONTROL ASSEMBLIES AND POSITION INDICATION SYSTEMS TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request:
Technical Specification Page 3/4.1.3.3 3/4 1-21 9804070142 980326 PDR ADOC~ 05000272 p
~ R!ACTIVI'!Y CO.L SYSTEMS ROD DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.3 The individual full length (shutdown and control) rod drop ti.me from 228 steps withdrawn shall be S 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
- a.
T
? 541°1, and avg
- b.
All reactor coolant pumps operating.
APPLICABILITY:~WLM!?-fMObE5 ', l f d.\\
ACTION:
c
- a.
With the drop ti.me of any full length rod determined to exceed the above limit, restore the rod drop ti.me to within the above limit prior to proceeding to MODE 1 or 2.
- b.
With the rod drop times within limits but determined with 3 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to S71% of RATED THERMAL POWER.
SURVEILLANCE REQUllEM!NTS 4.1.3.3 The rod drop time of full length rods* shall be demonstrated through measurement prior to reactor criticality:
- a.
For all rods following each removal of the reactor vessel head,
- b.
For specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and
- c.
At least once per 18 months.
SALEM - UNIT 1 3/4 1-21 Amendment No. 96