ML20073P936
| ML20073P936 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/14/1991 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20073P935 | List: |
| References | |
| NUDOCS 9105240193 | |
| Download: ML20073P936 (2) | |
Text
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4 Attachment IV to ET 91-0074 Page 1 of 2 ATTACIMENT IV PROPOSED TECilNICAL SPECIFICATION CIIANGE l
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9105240193 93o514 PDR ADOCK 05000482 P
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Attachment IV to ET 91-0074 Page 2 of 2 i
o REACilVITY CONTROL SYSTEMS ROD OROP TIME LlHITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length shutdown and control rod drop time from
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the physical fully withdrawn position shall be less than or equal to-e-2 seconds l
i from beginning of decay of stationary gripper coil voltage to dashpot entry with:
2.7 T,yg greater than or equal to 551'f, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY: H0 DES I and 2.
ACTION:
With the rod drop time of any full-length rod determined to exceed a.
the above limit, restore the red drop time to within the above limit prior to proceeding to MODE 1 cr 2.
b.
With the red drop times within limits but determined with three reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 66% of RATED THERKAL F0WER.
SURVEILLANCE REOUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:
For all rods following each removal of the reactor vessel head, a.
b.
for specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System ' hich could I
affect the drop time of.those specific rods, and c.
At least once per 18 months.
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