ML20040F897
| ML20040F897 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 02/04/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TASK-***, TASK-RR LAC-8067, NUDOCS 8202100443 | |
| Download: ML20040F897 (3) | |
Text
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1 D DA/RYLAND h
COOPERATNE po Box 817 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN 54601 (608) 788 4000 February 4, 1982 In reply, please refer to LAC-8067 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation
((p /
b ATTN:
Mr. Dennis M. Crutchfield, Chief 8
9 Operating Reactors Branch #5 Division of Operating Reactors 8
OCCT!!A73 10 U.
S. Nuclear Regulatory Commission
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C.
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SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
N PROVISIONAL OPERATING LICENSE NO. DPR-45 I
SYSTEMATIC EVALUATION PROGRAM (SEP) TOPIC STATU Gentlemen:
Following is a list of the remaining SEP topics assigned to the Licensee which will be completed and submitted to the tiRC by the end of February:
SEP Topic No.
Title II.2.C Atmospheric Transport and Diffusion Charac-teristics for Accident Analysis II.3.B Flooding Potential and Protection Require-ments II.3.B.1 Capability of Operating Plant to Cope with Design Basis Flooding Conditions II.4.F Settlement of Foundations and Buried Equipment III.3.A Effects of High Water Level on Structures III.3.C Inservice Inspection of Water Control Structures III.4.A Tornado Missiles III.4.B Turbine Missiles III.4.C Internally Generated Missiles a
6 0 6 9 82?2100443 820201 PDR ADOCK 05000409
-P PDR
r Mr. Dennis M. Crutchfield, Chief LAC-8067 Operating Reactors Branch #5 February 4, 1982 SEP Topic No.
Title III.5.A Effects of Pipe Break on Structures, Systems and Components Inside Containment VI.1 Organic Materials and Post Accident Chemistry IX.1 Fuel Storage IX.3 Station Service and Cooling Water Systems IX.5 Ventilation Systems XV.1 Decrease in Feedwater Temperature, Increase in Feedwater Flow, Increase in Steam Flow and Inadvertent Opening of a Steam Generator Relief of Safety Valve XV.5 Loss of Normal Feedwater Flow XV.7 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break XV.8 Control Rod Misoperation (System Malfunction or Operator Error)
XV.11 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position XV.13 Spectrum of Rod Drop Accidents (BWR)
XV.16 Radiological Consequences of Failure of Small Lines Carrying Primary Coolant Outside Con-tainment XV.18 Radiological Consequences of Main Steam Line Failure Outside Containment (BWR)
XV.19 Loss-of-Coolant Accidents Resulting from Spec-trum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary XV.20 Radiological Consequences of Fuel Damaging Accidents (Insida and Outside Containment)
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Mr. Dennis M. Crutchfield, Chief LAC-8067 Operating Reactors Branch #5 February 4, 1982 If you have any questions regarding this submittal, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE.
Frank Linder, General Manager FL:JDP:af cc:
J.- G. Keppler, Reg. Dir., NRC-DRO III NRC Resident Inspector J