ML20011A419
| ML20011A419 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/29/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20011A420 | List: |
| References | |
| LAC-7834, NUDOCS 8110130328 | |
| Download: ML20011A419 (2) | |
Text
-
DlDA/RYLAND h
k COOPERAT/VE
- PO box 817
(608) 788 4000 September 29, 1981 In reply, please refer to LAC-7834 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation A
httn:
Mr. Dennis M.
Cratchfisld, Chief
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'[
Operating Reactors Branch No. 5 6
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Division of Operating Reactors U.
- Nuclear Regulatory Commission El OCT 9 I90Ih '
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SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 N
3 l
NUREG 0737, ITEM II.K.3.30 4
l ADDITIONAL INFOM1ATION ON LOCA ANALYSIS I
REFERENCE:
(1)
NRC Letter, Eisenhut to All Licensees of Operating Plants, dated Octber 31, 1981
Dear Mr. Crutchfield:
Your request (Reference 1) for a review of small brcLk LOCA analysis to determine if compliance with 10 CFB 50, Appendix K was achieved, was reviewed by members of your staff and our consultant on February 11, 1981.
As a consequence of this discussion, it was determined that the staff would review LACBWR separately from the LOCA Models
'Ised for ECCS analysis by reactor vendors.
To facilitate this review five (5) copies of the attached ECCS related analysia are forwarded.
(1)
Gulf United Report SS-942, " Technical Evaluation of La Crosse Boiling Water Reactor Emergency Core Cooling System" datec May 31, 1972 (DPC transmittal letter to AEC dated June 5, 1972).
(2)
Gulf United Report SS-1075 (Rev. 1), " Response to Questions by AEC/DL With Regard to Gulf United Report I
SS-942, Technical Evaluation, Adequacy of La Crosse Boiling Water Reactor Emergency Core Cooling System",
Revised November 15, 1973.
y qp /r
, 8110130328 810929 0k PDR ADOCK 05000409 P
PDR h
9
o Mr. Dennis M.
Crutchfield September 29, 1981 U.
S.
Nuclear Regulatory Commission LAC-7834 (3)
Gulf Uni:ed Report SS-1085, " Review of Densificat..1 Effects in La Crosse Boiling Water Reactor", dated May 15, 1973.
(4)
Gulf United Repert SS-1126, " Supplemental Information on the La Crosse Boiling Water Reactor Emcrgency Core Cooling System", dated October 10, 1973.
(5)
NES Report 81A0244, " Comparison of LACBWR ECCS Results to AEC Final Acceptance Criteria" dated December 9, 1974.
(6)
NES Letter P-5101-240, " Reply to DL Questions Regarding NES 81A0244" dated June 18, 1975.
(7)
DPC Letter LAC-o 705, " Additional Infcrmation Required for NRC Staff Generic Report on Boiling Water Reactors" dated December 20, 1979.
(8)
DPC Letter LAC-3929 " Description of Exxon Type III Nuclear Fuel for Batch 1 Reload in the La Crosse Boiling Water Reactor ( LACBWR), dated May 18, 1976.
(9)
DPC Letter LAC-4374 Response to Questions on the Jycle 5
- Reload, dated December 9, 1978.
(10)
DPC Letter LAC-4440 Response to Questions on the Cycle 5 Reload, dated January 17, 1977.
If there are any further questions, please contact us.
Very tiuly yours, DAIRYLAND POWER COOPERATIVE chntlU&
uht e
Frank Linder, Gen'eral Manager FL:JDP:eme cc:
J.
G.
Keppler, Director, NRC-DRO III NRC Resident Inspectors
.