ML20003G465
| ML20003G465 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/24/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder J DAIRYLAND POWER COOPERATIVE |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR LSO5-81-04-044, LSO5-81-4-44, NUDOCS 8104290509 | |
| Download: ML20003G465 (4) | |
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April 24, 1981 Docket No. 50-409 LS05-81-04-044 grp [s U,7 h k0 Mr. Frank Linder General Manager
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Dear Mr. Linder:
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SUBJECT:
SEP TOPIC III-6, SEISMIC DESIGN CONSIDERATIONS LACROSSE Our letter to you dated August 4,1980 requested in accordance with 10 CFR 50.54(f) of the Commission's regulations that you submit plans and proceed with a seismic reevaluation program for the Lacrosse facility and that you provide justification for your conclusion that continued operation is justified in the interim until the seismic reevaluation program is cor@lete. We have reviewed your seismic reevaluation pro-gram forwarded by your letter dated October 14, 1980. We have determined that your program is deficient with respect to scope of structures, systems and components to be evaluated.
Our August 4,198010 CFR 50.54(f) letter specified as a minimum, that t
your program should provide for an evaluation of:
1.
The ir.tegrity of the reactor coolant pressure boundary, 2.
The integrity of fluid and electrical distribution systems related to safe shutdown and engineered safety features, and 3.
The integrity and functionability ct mechanical and electrical equipment and engineered safety feature systems (including con-tainment).
We have reviewed the systems at the Lacrosse facility which are impurtant to safety and should be included in your seismic reevaluation program.
These systems are identified in Enclosure (1).
You are requested to revise and resubmit within 30 days of receipt of this letter your seismic reevaluation program. Your revised program should include the systems identified in Enclosure (1) and their related structures and conponents. A schedule for completion of seismic reevalua-tions, submittal of analysis results for NRC review and the installation of any necessary modifications should be included in your revised program.
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Your schedule, if different from our August 4,1980 request, should be justified and should be consistent with your conclusion that continued operation is justified in the interim until the seismic reevaluation program is couplete and any necessary modifications are implemented.
Sincerely.
l Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 01 vision of 1.icensing
Enclosure:
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i April 24,1981
%,..... f Docket No. 50-409 L505-81-04-044 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601
Dear Mr. Linder:
SUBJECT:
SEP TOPIC III-6, SEISMIC DESIGN CONSIDERATIONS LACROSSE Our letter to you dated August 4,1980 requested in accordance with 10 CFR 50.54(f) of the Commission's regulations that you submit plans and 1
proceed with a seismic reevaluation program for the Lacrosse facility and that you provide justification for your ccr.clusion that continued operation is justified in the interim until the seismic reevaluation program is coglete.
We have reviewed your seismic reevaluation pro-gram forwarded by your letter dated October 14, 1980. We have determined that your program is deficient with respect to scope of structures, systems and co@onents to be evaluated.
l Our August 4,198010 CFR 50.54(f) letter specified as a minimum, that your program should provide for an evaluation of:
1.
The integrity of the reactor coolant pressure boundary, 2.
The integrity of fluid and electrical distribution systems related I
to safe shutdown and engineered safety features, and 3.
The integrity and functionability of mechanical and electrical equipment and engineered safety feature systems (including con-tainment).
We have reviewed the systems at the Lacrosse facility which are inportant to safety and should be included in your seismic reevaluation program.
These systems are identified in Enclosure (1).
You are requested to revise and resubmit within 30 days of receipt of this letter your seismic reevaluation program. Your revised program should include the systems identified in Enclosure (1) and their related structures and conponents. A schedule for completion of seismic reevalua-tions, submittal of analysis results for NRC review and the installation of any necessary modifications should be included in your revised program.
. Your schedule, if different from our August 4,1980 request, should be justified and should be consistent with your conclusion that continued operation is justified in the interim until the seismic reevaluation program is conplete and any necessary modifications are implemented.
Sincerely,
' 7A &JAhd Dennis M. Crutchfieli 'C/eT' Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
Se next page
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ENCLOSURE (1)
SAFETY RELATED SYSTEMS, STRUCTURES AND COMPONENTS LACROSSE PLANT The scope of review for the seismic re-evaluation program should include the systems, structures, and components (including emergency power supply and distribution, instrumentation, and actuation systems) with the following functions:
1.
The reactor coolant pressure boundary as well as the core and vessel internals. This should also include those portions of the main steam system up to but not including the turbine stop valve and connected piping of 2h inch or larger nominal pipe size, up to and including the first valve that is either normally closed or is capable of automatic closure during all modes of normal reactor operation.
2.
Systems or portions of systems that are required for safe shutdown as identified in the SEP safe shutdown review (SEP Topic VII-3). The system boundary includes those portions of the system required to perform the safety function and connected piping up to and including the first valve that is either normally closed or capable of automatic closure when the safety function is required.
3.
Systems or portions of systems that are required to mitigate design basis event:;, i.e., accidents and transients (SEP Topics XV-1 to XV-24). The functions to be provided include emergency core cooling, post-accident containment heat removal, post-accident containment atmosphere cleanup, as well as support systems, such as cooling water, needed for proper function-ing of these systems.
4.
Systems and structures required for fuel storage (SEP Topic IX-1).
Integrity of the pent fuel pool structure including the racks is needed.
Failure of the liner plate due to the safe shutdown earthquake must not result in significant radological releases, or in loss of ability to keep the fuel covered.
Failure of cooling water systems or other systems connected to the pool should not parmit draining of the fuel pool. Means to supply make-up to the pool as needed must be provided.
5.
Structures that house the above equipment.
For the Lacrosse Boiling Water Reactor plant, the staff considers the following systems, and associated structures, and components should be addressed:
a) Reactor Coolant System (RCS) b) Portions of Main Steam System c) Portions of Main Feedwater System
_2 d) Portions of systems directly connected to the RCS up to and including isolation valves e) Control Rod Drives f) Shutdown Condenser g) Portions of Demineralized Water Transfer or High Pressure Service Water System l
h) Portions of Hign Pressure Core Spray System i) Portions of Alternate Core Spray System j) Manual Depressurization System k) Spent Fuel Pool and Makeup Note:
The emergency service water supply system can supply water for post-earthquake and post-LOCA conditions provided parts of the above systems are intact.
As discussed above, a " system" also includes the power supply, instrumentation and actuation systems.
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