ML19208A871
| ML19208A871 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/09/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| TASK-03-02, TASK-03-03.A, TASK-03-07.B, TASK-3-2, TASK-3-3.A, TASK-3-7.B, TASK-RR NUDOCS 7909180101 | |
| Download: ML19208A871 (3) | |
Text
TErca m uta UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 E
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%J.....J August 9, 1979 Docket No. 50-409 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601
Dear Mr. Linder:
RE:
REQUEST FOR ADDITIONAL INFORMATION SYSTEMATIC EVALUATION PROGRAM STRUCTURAL TOPICS LACROSSE BOILING WATER REACTOR To continue our review of the Systematic Evaluation Program structural topics, we request that you provide the information described in the enclosure for each of the identified topics.
Your response is requested within 30 days so that we can maintain our review schedule.
Sincerely, C b.v m T
Dennis L. Ziemann,' hief Operating Reactors Branch #2 Division of Operating Reactors
Enclosure:
Request for Additional Information cc w/enclosurer See next page
% S003 790918oiOl P
Mr. Frank Linder August 9,1979 ccFritz Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 54601
- 0. S. Heistand, Jr., Esquire Morgan, Lewis & Bockius 1800 M Street, N. W.
Washington, D. C.
20035 Mr. R. E. Shimshak La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 135 Genoa, Wisconsin 54632 Coulee Region Energy Coalition ATTN:
George R.- Nygaard P. O. Box 1583 La Crosse, Wisconsin 54601 La Crosse Public Library 800 Main Street La Crosse, Wisconsin 54601 K M C Inc.
ATTN: Mr. Richard E. Schaffstall 1747 Per^sylvania Avenue, N. W.
Suite 1050 Washington, D. C.
20006 358004
tnclosure LACROSSE BOILING WATER REACTOR REQUEST FOR ADDITIONAL INFORMATION FOR STRUCTURAL TOPICS III-2 Wind and Tornado Loads Specify specific tables and sections of ASCE paper 3269 that were used in the design considerations of wind loading of the plant.
III-3.A Effects of High Water Level on Structures For each of the safety-related structures state the water level that was considered in the design.
III-7.B Design Codes, Design Criteria, Load Combination, and Reactor Cavity Design Criteria 1.
Provide detailed descriptions of the containment and the internal structures of the plant.
2.
With regard to the design of the containment and the internal structures, provide the design specifications and appropriate design reports. This information should include the infortnation requested in items three thrcugh seven below.
3.
List the codes and standards (including edition date) used for design and construction of all safety-related structures, including the allowable stresses used in design.
4.
List all loads and load combinations considered in the design of each safety-related structure, including any m'ssile or pipe break effects.
5.
Provide the pertinent material properties of the steel and concrete used in the design of all safety-related st'.uctures (i.e., fy, fc, etc.).
6.
Provide a sumary of stresses or strains at critical locations in all safety-related structures for each load and load combination considered in the design.
7.
Provide the buckling criteria used for design of the steel containment.
III-7.D Containment Structural Integrity Tests Provide any reports that describe the procedures and results of the primary containment structural integrity test.
358005