ML20011A435
| ML20011A435 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/18/1974 |
| From: | Madgett J AUTOMATION INDUSTRIES, INC. |
| To: | Goller K US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20011A420 | List: |
| References | |
| NUDOCS 8110130345 | |
| Download: ML20011A435 (3) | |
Text
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c AUTOMATION INDUSTRIES, INC.
NUCLEAR ENERGY SERVICES DIVISION SHEsf E4 ROCK ROAD
- g. C-CANeumv. CONNECT Cut 06810 u 3 A.
aan tse-ase December 18, 1974 l
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Mr. Karl R. Goller Assistant Director for Operating Reactors Directorate of Licensing
Dear Mr. Goller:
With regards to your May 8, 1974 and September 18, 1974 letter to Dairyland Power Cooperative 4pproving our fuel densification model and requesting an evaluation of LACBWR fuel to the new ECCS criteria, we have enclosed for your review and evaluation the information and supporting statements concerning the current La Crosse Boiling Water Reactor (LACb 3) fuel design to 10CFR50.46 and Appendix K Acceptance Criteria for ECCS for Light Water Reactors.
In order to determine the adequacy of the existing LACBWR fuel to the final criteria, the attached document, " Comparison of LACBWR ECCS Results to AEC Final Acceptance Criteria" t4ES 81A0244, 12/9/74, is submitted.
The comparison demonstrates that the LACBWR facility g
meets the technical basis of 10CFR50.46 for the stainless steel clad fuel currently in operation.
The LACBWR Emergency Core Cooling System is capable of providing cdequate cooling for all postulated LOCA conditions and maintains fuel rod integrity during both the short term and long term cooling periods with substantial margins of safety.
If you have further questions with regard to this submittal, we will be happy to discuss them with you at your convenience.
Sincerely, John P. Madgett General Manager DAIRYLAtlD POWER COOPERATIVE JPM:vad cc:
A. Giambusso l
Deputy Director for Reactor Projects Directorate of Licensing i
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. 3 AUTOMATIOi! INDUSTRIES, INC.
4 NUCLEAR ENERGY SERVICES DIVISION SHELTER ROCM ACAO DA%SURY. CONNEC?tCUT 06810 U S A.
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(203) 748-3581 December 10, 1974 Reference No, P-5101-79 Mr. R. E. Shimshek Lacrosse Boiling Water Reactor DAIRYLAND POWER COOPERATIVE P. O. Box 135 Genoa, Wisconsin 54632
Subject:
Comparison of LACBM ECCS Results to AEC Final Acceptan".a Critiera, NES 81A0244
Dear Dick:
Enclosed is the evaluation of the current LACBWR fuel design to 10 CFR 50.46 and Appendix K.
This will satisfy the AEC requirements as definad in the AEC ', letter to OPC of May 8, 1974.
The evaluation is a comparison of the o r i-
'l LOCA/ECCS analysis (performed to the interim criteria) to the final er._eria requirements.
The sequence of events that I see evolving is as follows:
1.
Submission of the enclosed comparison with a strong, positive statement that the LACBWR fuel and plant systems meet the technical Sases underlying the final criteria.
2.
Submission of the ECCS analysis for the Exxon reload fuel to the interim critiera showing that its im-proved design will result in lower cladding tempera-tures than the current LACBWR fuel (core 1 and 2).
3 Conclusion from 1 and 2 above that the Enon fuel satisfies the final criteria since it is a better design (Iower max cladding temperature) than the current fuel.
This conclusion will be valid if the AEC accepts the enclosed comparison as proof of the final criteria.
Therefore, I suggest that your forwarding letter to the AEC include a para-graph similar to the following:
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f R. E. Shimshak 12/10/74 LACBWR P-5101-79 "The AEC letter of May 8, 1974 noted that the final criteria and associated model features were established for light-water reactors using fuel with zircolay cladding.
However, the technical information underlying a number of the requirements is also applicable to stainless steel clad fuel.
In order to determine the adequacy of the existing LACBWR fuel to the final criteria, the attached comparison was made of the loss-of-coolant accident analysis, previously submitted to AEC-DL, to the final criteria and Appendix K model requirements.
The comparison demonstrates that the LACBWR facility meets the technical bases underlying the final criteria requirements of 10 CFR 50.46 for the stainless steel clad fuel currently in operation.
That is, the LACBWR Emergency Core Cooling System is capable of providing adequate cooling for all postulated loss-of-coolant accident conditions and maintains fuel rod Integrity during both the short term and long term cooling periods with substantial margins of safety."
l would not recommend mentioning Exxon fuel in the letter so as to keep the AEC attention focused on current fuel adequa y.
After that is resolved, the logic will be established for obtaining reload fuel approval.
Sincerely, AUTOMATION INDUSTRIES, INC.
NUCLEAR ENERGY SERVICES OlVISION William J. Manion Vice President and General Manager WJM:rbp Enclosures
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