ML19318B006
| ML19318B006 | |
| Person / Time | |
|---|---|
| Site: | 07001201 |
| Issue date: | 05/06/1980 |
| From: | Zeff D BABCOCK & WILCOX CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML19318B007 | List: |
| References | |
| 16273, NUDOCS 8006240515 | |
| Download: ML19318B006 (3) | |
Text
- e QDp 70-'
Bab. cock &Wilcox C
... aiuoe w oeieant
.O. Box 800, Lynchburg, Va. 24505 P
Telephone: (804) 384.5111 May 6, 1980 Mr. I..
C. Rouse, Chief Fuel Processing 6 Fabrication Branch Office of Nuclear >!aterial Safety and Safeguards Division of Fual Cycle 6 hiatorial Safety United States Nuclear Regulatory Commission Washington, D. C.
20555
REFERENCES:
(1) SNh!-1168, Docket 70-1201 (2) Amendment Application No. 79-3, Dated January 9,1980
Subject:
Ah!ENDb!EVT APPLICATION NO. 79-3 Gentlemen:
The Babcock 6 Wilcox Company Commercial Nuclear Fuel' Plant requests amendment of License Number SNbi-1168 as previously discussed with =cmbers of your staff. The $1400 minor safety amendment licensing fee as required by 10 CFP. 170 was submitted with the January 9, 1980 submittal (B6W Check Number 23345).
The areas addressed in the amendment request are as follows:
- Revision of action levels for air effluent releases to unrestricted areas. Revised levels are needed in order to allow for routine localized operations involving pellets outside the controlled area.
A se.*ies of detailed controlled experiments were performed to deter-mine appropriate controls for maintaining airborne concentrations in such areas as low as reasonably achievable.
During the two calendar quarters that the experiments were performed, extensive surface con-tamination surveys were conducted in the area.
Results of these surveys revealed no new health and safety concerns since existing controls and limits for the uncontrolled area were not exceeded.
Based on these tests and experiments, the most effective air-capture technique was selected for implementation, and we are therefore re-questing a corresponding revision of the action level.
800624 09 (
ym The Babcock & Wilcox Company / Established 1867
c Babcock &Wilcox Mr. L. C. Rouse, Chief Page 2 May 6, 1980
- Revision of action levels for liquid effluent releases.
In the past, routine effluent releases from the CNFP retention tank had been at levels requiring approval and/or further dilution prior to release. An ultrafilter system was subsequently purchased and installed at a cost of approximately $30,000 to remove the uranium particulate from certain liquid streams entering the reten-tion tank.
The addition of the ultrafilter significantly reduced release levels, but there are cases where the " cleaned" water from the ultrafilter may not be diluted by the other liquid waste streams (i.e., during periods of plant shutdown, etc.) and therefore would be the only input to the retention tank. This " cleaned" ultrafilter water generally has contamination levels at 20% FFC or below which would exceed the present release levels. The overall effectiveness of the ultrafilter system in removing uranium particulate has been excellent; releases to the environment are approximately one third of the IcVels experienced prior to using the ultrafiltration system. Therefore,
the requested 20% action level is not intended to increase radio-activity in effluent releases, but only to reduce the administrative paperwork required during periods of low flow.
- Revision of isolation criteria between fuel assembly storage array and fuel assembly shipping container loading area.
Sections III and V of SNM-1168 presently address the fuel assembly processing and storage area as a single array, with other arrays isolated from it.
Due to limited existing floorspace and the potential need to expand the fuel assembly storage capacity, the fuel assembly shipping container loading area will need to be located closer to the assembly storage rack.
Section 7.10.3 of Section V of SNM-1168 states that fuel assemblies in adjacent containers will be separated by not less than 18 inches edge to edge.
Pages 184-193 and 196-200 in Section III of SNM-1168 demonstrates the safety of an infinite storage array of fuel assemblies and an infinite array of damaged shipping containers respectively.
Results show that under all credible conditions the shipping container array is the more reactive of the two.
In addition, it has been determined that the 38" center-to-center distance betwen two loaded containers is equivalent to 18" edge-to-edge separation between assemblies in adjacent containers. Thus, 38" center separation between the storage array and the loading area will provide acceepta-ble nuclear interaction control. Any activity equally or less reactive than the loaded shipping containers may be conducted at the same sepa-ration distance away from the fuel assembly storage rack.
Rahrw+ &Wilcox Mr. L. C. Rouse, Chief Page 3 May 6, 1980
- Revised contamination survey frequency.
Presently, we are required to perform daily surveys of the lunchroom and locker-room areas even during periods of plant shutdown and vacation.
Data from previous quarters consistently show that contamination levels at the lunchroom area during normal powder processing operations have been near :ero or at the minimum detectable level as shown below.
Smear Total Survey Average Survey Average 1st quarter 1979 4.3 DPM/100 cm.,
< 100 DPM/50 cm 2nd quarter 1979 2.6 DPM/100 cm;
<100DPM/50cm; 3rd quarter 1979
< 1 DPM/100 cm'
< 100 DPM/50 cm; 4th quarter 1979 0.0 DPM/100 cm.,
< 100 DPM/50 cm; 1st quarter 1980 0.0 DPM/100 cm'
< 100 DPM/50 cm' The data summary above clearly shows that such areas do not have a meaningful potential for contamination. The sontrols placed on personnel and equipment exiting the controlled area effectively precludes contamination spread, and therefore the associated survey frequency could be relaxed without sacrificing employee health and safety.
If you or members of your staff have any questions regarding the above items, please feel free to call me or J. P. Watters at (804) 384-5111.
Sincerely, BABCOCK G WILCOX COMPANY CastERCIAL NUCLEAR FUEL PIAVT e-.
/
D. W. Ze f, nager Health-Safet' /ahd Licensing y
DWZ:can Attachment cc:
J. P. Watters (w/ attachment)
W. F. Heer (w/o attachment)
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