ML18106A429

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Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A429
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/26/1998
From:
Public Service Enterprise Group
To:
Shared Package
ML18106A428 List:
References
NUDOCS 9804070142
Download: ML18106A429 (2)


Text

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  • Document Control Desk Attachment 3
  • 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 PDR

~ 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CONDITION FOR OPERATION 3.1.3.3 The individual full length (shutdown and control) rod drop ti.me from 228 steps withdrawn shall be S 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with: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. Tavg ? 541°1, and
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