ML20236C815
| ML20236C815 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/21/1987 |
| From: | Standerfer F GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 4410-87-L-0127, 4410-87-L-127, NUDOCS 8710270348 | |
| Download: ML20236C815 (14) | |
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k GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South s
Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
(717) 948-8461 October 21, 1987 4410-87-L-0127/0214P b
R C:
US Nuclear Regulatory Commission
~ 93 Attn: Document Control Desk
.j 56 '
Washington, DC 20555 7'
\\
> C3
Dear Sirs:
g Three Mile Island Nuclear Station, Unit 2 (TMI-2)
U Operating License No. DPR-73 Docket No. 50-320 Defueling Canister Gas Sampling The purpose of this letter is to request NRC approval to discontinue the long-term gas sampline program at the Idaho National Engineering Laboratory (INEL).
The NRC TMICPD Letter NRC/TMI-87-003, dated January 7, 1987, approved a GPU Nuclear request to reduce the required canister void volume to 25% for fuel canisters and to levels assuring exposure of 25 grams of recombiner catalyst for filter and knockout canisters.
The NRC approval was granted provided the following conditions were met:
1.
Canisters would be dewatered to the maximum extent practical.
2.
After shipping, confirmatory gas measurements would be taken on one (1) canister per shipment (i.e., one (1) of seven (7) for a single cask shipment, one (1) of 14 for a double cask shipment).
A gas sample would be withdrawn and analyzed shortly after (i.e., within a few days) removal of the canister from the shipping cask at the INEL.
Subsequently, the canister would be stored in an unvented condition for about six (6) weeks and resampled.
The gas sample analysis would be used to confirm the conservatism in the projected 8
allowable shipping window, as determined by comparison with gas samples withdrawn prior to shipping.
3.
The sample results would be made available for NRC review upon request.
h 0
D gp P
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I GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation jg c p w /c areg 4= 0 076 06
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Document Control Desk October 21, 1987 4410-87-L-0127 The intent of the long-term gas sampling program described above in item No. 2 is to verify 1) the catalyst recombiner is functioning under shipping conditions, 2) a combustible mixture of oxygen and hydrogen is not being shipped, and 3) the absence of an excessive pressure rise in the canisters due to a net hydrogen increase.
Based on the justification provided below, GPU l
Nuclear believes that the long-term gas sampling program is no longer l
necessary.
l To date, a total of eight (8) canisters have been sampled at INEL (several of the canisters have been sampled several times). presents the gas sample results from both TMI and INEL in tabular form.
This table provides i
the number of gas samples per canister at TMI and INEL, the number of days between samples, and the gas sample chemical analysis results. Attachment 2 graphically displays the gas sample data of Attachment 1.
The graphs compare the percentage of hydrogen and oxygen present in the TMI and INEL samples as a function of the number of days after dewatering.
The following conclusions can be made from reviewing the attachments:
o At no time during the sampling program was a combustible mixture of gas approached, o
In each case, the sample results obtained at TMI are conservative in determining the gas appearance rate, i.e., if employing the single point straight line projection shown in Attachment 2, the safe storage time calculated using the TMI data is less than the safe storage time calculated using the INEL data, o
In all cases where oxygen scavenging was apparent, the hydrogen appearance rate was found to be less than 10 percent of the theoretical maximum used in previous analyses, o
A pressure increase due to net hydrogen production is not detectable.
After dewatering, the canisters are overpressurized with argon to approximately 2 atm (29.4 psi). The highest canister pressure that has been observed at INEL is 29.33 psi (i.e., also approximately 2 atm).
The canister design pressure is 150 psig.
GPU Nuclear believes that the data generated at INEL on the eight (8) canisters sampled, provides a sufficient data base to conclude that no safety
^
hazards exist due to combustible gas mixtures or canister overpressurization.
The safe shipment time calculated at TMI is more than adequate to meet the requirements of the NuPac 1258 Certificate of Compliance (C of C) and the Canister Handling and Preparation for Shipment Safety Evaluation Report.
Therefore, GPU Nuclear requests approval to discontinue the long-term sampling program at INEL.
Per the requirements of 10 CFR 170, an application fee of $150.00 is enclosed.
Sincerely, 64 "V
F. R. Standerfer Director, TMI-2 CI/eml
l Document Control' Desk October 21, 1987 4410-87-L-0127 Attachment Enclosed: GPU Nuclear Corp. Check No. 007606 cc: Regional Administrator, Region 1 - W. T. Russell Director, TMI-2 Cleanup Project Directorate - Dr. W. D. Travers l
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