ML20237H681
| ML20237H681 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 08/20/1987 |
| From: | Bidinger G, Swift J NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20237H635 | List: |
| References | |
| NUDOCS 8708250109 | |
| Download: ML20237H681 (2) | |
Text
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MG 2 01987 IMUF:GHB f
(
DOCKET N0:
70-1100 LICENSEE:
Combustion Engineering, Inc. (CE)
Windsor, Connecticut
SUBJECT:
SAFETY EVALUATION REPORT, REVISED LICENSE APPLICATION DATED JULY 24, 1987, RE VODERATION CONTROL CRITERIA Fackground On December 17, 1986, CE submitted an application to revise nuclear criticality safety criteria for moderation control. As a result of a meeting on February 18, 1987, the application was completely revised on March 18, 1987.
Following a second meeting on July 13-14, 1987, the subject application wer submitted. The proposed amendment separates the criteria for optimum moderation and controlled moderation as well as revises the previously proposed controlled moderation criteria.
Discussion CE has revised Section 4.2.4, Part I, and added Section 4.2.4A, Part 1.
Criteria in Section 4.2.4 which can be used in all areas of the plant provide for optimum moderation and reflection. This revised section is essentially the same as several years ago before limited moderation control criteria were introduced.
The revised criteria for limited moderation provide for controls on the fire suppression water sprinkler system, consideration of the water film thickness on fuel rodt, and validation of and limits for k-effective calculations. These criteria will be used only in the fuel rod processing and fuel assembly handling and storage areas. The criteria are not adequate for powder or pellet handling areas.
In the Safety Demonstration Section, CE provided calculations for the density of water falling from sprinklers. The calculations were made by Factory Mutual Research Corporation, who designed the sprinkler system to NFPA standards. The water film thickness on the fuel rods was calculated by CE. The calculations were reviewed by Dr. Novak Zuber, RES, and found to be acceptable. CE has performed a limited number of calculations to validate the CE cross-sections and the CE version of KENO-IV. Because of the limited benchmark experiments, CE increased the uncertainty resulting from the validation effort by a factor of 5.
(Due to a typographic error, the factor appears to be 0.5.
According to R. Sheerin on August 18, 1987, tr.is will be corrected in the next licensing
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87082D0109 870820 DR ADOCK 0700 0
Combustion Engineering, Inc., SER 2
The NRC staff performed a series of calculations to evaluate the proposed criteria for various array sizes, assembly pitches, mist densities, film thicknesses, and cross-section sets. The staff's calculations were in agreement with the CE calculations.
Conclusion / Recommendations l
The staff concludes that the proposed criteria are adequate for processing and
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storage of fuel rods and assemblies in moderation controlled areas. Approval of the application is recommended.
The NRC Region I Principal Inspector has no objection to this action.
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Original Signed By:
George H. Bidinger Uranium Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety, NMSS l
Aicinal Signed Fy g
Jerry J. Swift, Section Leader OFC:IMUF g3
- IMUF MU j
- IMSE NAME:GHBidinger:ht
- YLTharpe 2 5 wift
- L suse DATE:08//9/87
- 08/\\S/87
- 08/w/87
- 08
/87 0FFICIAL RECORD COPY
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