ML20236U547
| ML20236U547 | |
| Person / Time | |
|---|---|
| Site: | 07003089 |
| Issue date: | 07/24/1998 |
| From: | Persinko D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Pierson R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9807300268 | |
| Download: ML20236U547 (60) | |
Text
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.Tuly 24, 1998 i .
i l
TO; l'
. Robert C. Pierson, Chief Special Projects Branch, NMSS FROM: Drew Persinko, AVLIS Project Manager l
Special Projects Branch, NMSS !
SUBJECT:
MEETING
SUMMARY
FOR MEETING WITH U.S. ENRICHMENT CORPORATION TO DISCUSS CRITICALITY SAFETY VALIDATION REPORT
References:
- 1) AVLIS Criticality Code Validation Report, USEC to NRC, April 22,1998
- 2) Staff Request for AdditionalInformation, NRC to USEC, June 10,1998 On July 21,1998, NMSS/SPB staff met with staff from the U.S. Enrichment Corporation l>
(USEC) and their contractor, B&W, to discuss the nuclear criticality safety validation report (Reference 1), submitted to support the licensing of the Atomic Vapor Laser Isotope Separation (AVLIS) technology, and responses to staff questions (Reference 2) on the report. USEC is requesting NRC to license the AVLIS facility up to a uranium enrichment of 10 percent. The nuclear criticality safety validation report was submitted to support this enrichment level. The j staff will consider the information presented at the meeting and review the information provided j at the meeting and determine whether any additional information is necessary for the staff to write a Safety Evaluation Report.
Discussion points addressing the staff's questions on the nuclear criticality safety validation report are provided as Attachment 1. Slides used in the meeting are provided as Attachment 2.
A list of meeting attendees is provided as Attachment 3.
USEC intends to submit an AVLIS license application in February 1999; however, non-site-specific information is being submitted for staff review before the application is submitted. The criticality safety validation report and this moeting were part of the ongoing pre-license application activities.
Attachments: As stated cc: R. Woolley, USEC
/
l DISTRIBUTION:
Docket 70-3089 Central File PUBLIC NMSS R/F FCSS R/F SPB R/F -
OFC _SPB bmSih ,[ S_P_B # SM SPB NAME bPersinko:ij ey / M in L DATE 1'Nf98 8 73f[98 1 M/98 / /98 C = COVER E =' COVER & ENCLOSURE N = NO COPY mtsumcrt.721 OFFICIAL RECORD COPY l 9
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i Cross Section Library Figure C: Calculated Minimum Margin of Suberiticality Based on the Method in NUREG/CR-6361.
The Recommended Safety Limit in the AVLIS validation report was developed using a somewhat different statistical approach. The calculational results were tested to determine if trends existed. Linear least square fits were determined for selected key parameters (IVX, ECALCF, enrichment, etc.). The correlation coetlicient (R2 ) was determined for these fits. If it was below 0.5, no trend was assumed to exist. For the parameters ofinterest, no significant trends were evident. The Validation Report shows the data to be normally distributed. The Lower Tolerance Limit (LTL) was developed for a 0.95/0.99 percent confidence level. The pooled variance used in establishing the LTL was the sum of the variance about the mean, the variance of the calculations and the variance of the experimental uncertainties. The Recommended Safety Limit was then established as the LTL minus the margin of suberiticality (0.02 Ak).
In comparing the USL and the Recommended Safety Limit, the Recommended Safety Limit is lower than the USL in all cases (see Figure D). The Recommended Safety Limit is the Lower Tolerance Limit (LTL) minus the margin of suberiticality. Since the Recommended Safety Limit is less than the USL, the AVLIS method of validation is more conservative than the method specified in NUREG/CR-6361. The USL and the l Recommended Safety Limit for each of the three parameters (enrichment, IVX, and ECALCF) and the three cross section libraries are shown in Figures E-M.
l Page 8 of 24
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l Leu-comp-therm-024c1 0.674 0.244 0.082 i
l Leu-comp-therm-026c2 0.800 0.132 0.068 Leu-comp-therm-026c4 0.670 0.221 0.109 y-dr-81_t2e4 0.220 0.171 0.609 y-dr-81_t2e5 0.212 0.186 0.601 y-dr-8l_t2e21 0.257 0.227 0.517 y-dr-81_t2e25 0.183 0.177 0.640 y-dr-8 l_t4e97 0.091 0.228 0.681 y-dr-81_t4e98 0.094 0.260 0.647 y-dr-81_t6e8 0.111 0.204 0.685 l
Page 14 of 24
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a Table D Fission Fractions for a Water Reflected Damp Oxide Systems UO2 Mass Weight ECALCF Thernial Intermediate Fast (kg) Fraction of (eV) (<0.625 eV) (>0.1 MeV)
IIydregen (II/U) 5300 0 7200 0.180 0.334 0.486 (0) 5400 1.02x10 7300 0.173 0.342 0.485 .
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I ATTACHMENT 3 ATTENDEES i i
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- Attachment 3 Meetina Attendees Name Organization Drew Persinko NRC Robert Pierson NRC Dan Martin - NRC Kim Hardin NRC
' Christopher Tripp NRC Charles Nilson NRC Harry Felsher NRC James Slider USEC Marc Klasky USEC Larry Wetzel USEC/BWXT Brian Kidd USEC/BWXT Francis Alcorn USEC/BWXT via conference phone:
Robert Woolley USEC Ron Koopman USEC Christa Boman USEC Mark Michaelson USEC l
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