ML20151D674
| ML20151D674 | |
| Person / Time | |
|---|---|
| Site: | 07000824 |
| Issue date: | 03/30/1988 |
| From: | Olsen A BABCOCK & WILCOX CO. |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 29186, NUDOCS 8804140361 | |
| Download: ML20151D674 (13) | |
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$.6 Babcock & Wilcox NNFD REsEARCH LABORATORY 6
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{9 (804) 522 6000 March 30, 1988 WA d P DV s
s Fuel Cycle Safety Branch ATTN: Mr. L. C. Rouse, Chief Division of Industrial & Medical Nuclear Safety NMSS U. S. Nuclear Regulatory Commission Washington, DC 20555
Reference:
License No. SNM-778, Docket 70-824
Subject:
Amendment No. 4, additional information.
Gentlemen:
My letter dated December 8,1987, forwarded an application for Amend-ment No. 4 to the referenced license.
The application provides for an additional storage facility for waste generated in our hot cells.
In response to the application. I have received telephoned requests for additional information.
This is in response to those requests.
My notes of the phone conversations indicate the infornation requested is as follows:
1.
Provide the radiation level that served as the basis for the 24-inch thick concrete shielding at the top of the silos.
2.
The sample frequency specified for the Temporary Stor-age Facility in Section 5.2.2.9 should be changed to "once each quarter." Also, in the same section, specify that the sample will be analyzed and that if contami-nation is found, corrective action will be taken to prevent further leakage.
The action level of 10% of the Appendix B, Table 2, Column 2 value should be changed.
3.
In Section 5.2.2, add a requirement that if contami-nation is found as a result of above analysis, Sections 7.2.3.8 and 7.4.1 will be amended to incorporate the Temporary Storage Facility into the general plan for decomissioning.
4.
Please add the figure number to the drawing found on page 10-15.
8804140361 080330 PDR ADOCK 07000824 C
PDR G
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5.
In Section 4.2.4.1, provide a description of the method used to assure that the amount of SNM in a waste con-tainer does not exceed 45-grams, and specify the mini-mum size of the waste containers.
C.
Explain what is meant by the term "Dry Waste."
Responses to the above requests are provided in the replacement pages for the license application manual that are attached.
An explanation of the changes and an instruction sheet for entering the pages in the manual are also orovided.
In addition to the specific information requested above, Dr. Soong reques ted any information tha t may be available that would demonstrate that the containers could be expected to maintain their integrity for up to thirty years.
That information is not yet available, but it has been requested.
I will forward it when it becomes available.
Dr. Soong also requested informa tion that would indica te that a bottom waste drum will withstand the weight of a column of typically loaded drums under the anticipated storage arrangements. This infor-mation is also under development and I will forward it when it becomes available.
Very truly yours, BABC0CK & WILC0X NNFD Research Laboratory C
A. F. Olsen Senior License Administrator jhc Attachment 1
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t DESCRIPTION OF CHANGES DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 BAW-381 AMENDMENT NO. 4 REVISION N0. 9 MARCH, 1988 Page Section Change 4-10 4.2.4.1 The section has been changed to add a definition of "Dry Waste," specify the minimum size of waste con-tainers, and to describe the method of accounting for SNM in irradiated fuel.
5-4 5.2.2 Item No. 9 was revised to read as it did prior to Revision No. 8.
Item No.10 has been added to increase the sample fre-quency of the Temporary Storage Facility from annually to quarterly, to specify that the sample will be ana-
- 1) zed, and that the action level has been changed from 10% of 10 CFR 20, Appendix B, Table 2, Column 2, to 30 pC1/L Beta-Gamma. There is also a requirement that if contamination is found, corrective action will be taken in a timely manner, and that the Temporary Storage Facility will be included in the Section 7, decommissioning' plan if contamination is found.
10-6 10.4.2.7 The basis for the 24-inch thick concrete lid has been added.
10-15 Fig. 10-5 The Figure number was added.
4 14-16 14.3.4 The section has been changed to add a definition of "Dry Waste." specify the minimum size of waste con-tainers, and the describe the method of accounting for SNM in irradiated fuel.
14-18 No change.
14-19 No change.
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l INSTRUCTION SHEET BAW-381 DEMONSTRATION AND CONDITIONS FOR LICENSE SNM-778 REVISION 9 AMENDMENT 4 1
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Da te Page Rev.
Da te 4-10 8
11/87 4-10 9
3/88 j
5-4 8
11/87 5-4 9
3/88 l
10-6 8
11/87 10-6 9
3/88 I
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11/87 10-15 9'
3/88 1
14-16 8
11/87 14-16 9
3/88 14-17 8
11/87 14-17 9
3/88 14-18 8
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Scrap, including rod segments, shall be disposed of according to present LRC procedures and limits.
4.2.3 Outside Storage 4.2.3.1 General - Outside storage consists of underground storage, ship-ments, and the fenced storage area located adjacent to Building J.
4.2.3.2 Underground Storage - Radioactive materials stored in underground storage tubes shall be limited to one SNM unit per tube, with values as specified in section 4.2.2.2 of this Part. Tubes shall be spaced 20-inches center-to-center and are 5-inches in diameter, and totally immersed in concrete.
4.2.3.3 Shipments - Each shipment of fissile material being stored out-side must conform with all license requirements for the type of shipping container.
Additionally, each shipment must ae nuclearly isolated from all other SNM.
4.2.4 Dry Waste 4.2.4.1 Dry waste is waste that is free of liquids but not necessarily free of hydrogenous material.
Dry waste shall be accumulated in steel drums or steel containers with a minimum size of 30 gallons (114 liters) and a maximum of 45 grams of SNM per container.
These con-(
tainers may be located throughout the laboratories as required to
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collect contaminated laboratory waste.
Filled containers are trans-ferred to either the radioactive waste storage building or to the temporary storage facility.
Containers of unirradiated SNM shall be gamma scanned before transfer to verify that the 45 grams SNM per container limit is not exceeded. Drums containing irradiated SNM are not gamma scanned. The amount of SNM per container is based on a mass balance difference.
The amount of waste generated within any hot cell or unit handling irradiated fuel is equal to the difference between the mass of SNM transferred into the unit, less the mass of SNM transferred out.
Dry waste in ;ontainers with less than 0.5 grams of unirradiated SNM per container may be stored in the fenced, locked and paved outside storage area adjacent to Building J.
March, 1988 License No SNM 778 Docket No.70-824 Date 4
9 4-10 g
Amendment No.
Revision No.
Pm U
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e 8.
Direct radiation monitoring at the site boundary -
continuously.
9.
Accumulated water from the soil retention basin shall be sampled annually and if its activity exceeds 10% of the concentration specified in Appendix B, Table 2, Column 2, of 10 CFR 20, the collected water shall be disposed of through the liquid waste disposal system.
- 10. Accumulated water from the Temporary Storage Facility shall be sampled and analyzed once each calendar quarter and if activity exceeds 30 pCi/L Beta-Gama, an investigation shall be made to determine the cause.
If the leak is from a waste container, action will be taken to prevent further contamination.
If con-tamination is found, Sub-sections 7.2.3.8 and 7.4.1 of this application shall be amended to incorporate the decommissioning of the Temporary Storage Facility.
5.2.3 The evaluation of environmental sampling shall be performed by either the site personnel or a qualified outside concern.
O l
l March, 1988 License No SNM 778 Docket No.70-824 Date 4
9 5-4 O
Amendment No.
Revision No.
Page Babcock &Wilcox a McDermott company i
i are loaded into the Annex from the top.
A curbing will be placed
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O on the approach side of the addition to prevent a loading v,ehicle from accidentally contacting the wall.
Two individuals are involved in loading containers into this facility to prevent a container from striking the walls.
This facility provides storage of waste that is contaminated with irradiated fuel and is being stored on site until it is accepted by the DOE under the Nuclear Waste Policy Act of 1982.
The maximum quantity of SNM per container shall be limited to 45 grams.
10.4.2.5 The Outside Waste Storage Area is located adjacent to Building J.
This area is fenced, locked and paved.
Waste stored in this area is limited to tha t contained in closed metal containers.
Each container is limited to not more than a Type A quantity (10 CFR 71.4) or 0.5 grams of fissile material or both.
Pu shall not be stored in this area. Containment of stored waste is assured by a quarterly visual inspection by the Supervisor, Health and Safety, 10.4.2.6 The High Level Waste Storage Tubes are located adjacent to the south side of the Liquid Waste Disposal Facility.
These tubes are constructed of two sections of iron pipe, immersed in concrete, and below ground level.
The upper section of pipe (approximately 42-inches long) is 6-inches in diameter.
The lower section (approximately 80-inches long) is welded to the upper section and is 5-inches in diameter.
Each tube is fitted with a concrete-filled iron plug.
These tubes are locked and O
under the direct control of the Health and Safety Group.
Waste stored in these tubes is limited to that which is produced in the Hot Cells and must be in closed metal containers. The quantity of fissile material permitted in each tube is limited to one unit.
10.4.2.7 The Temporary Storage Facility is located ad.iacent to the Reten-tion Basin, within the fenced and locked restricted area (Fig.
10-1).
This facility (Fig. 10-3) consists of an in-groLnd array of eight vertical, concrete "silos" arranged in two rows of four.
The silos rest on a common concrete pad and are surrounded at the top by a concrete apron that promotes rain water runoff.
Each silo is equipped with a 24-inch thick concrete lid.
The lid thickness is based on a radiation level of 5 R/hr from the column of drums within a silo.
The foundation drain system, at the base, is piped to a collection tank to permit periodic sampling.
Each silo is equipped with a stainless steel drain pipe which leads to a common sampling pit. The waste that is stored in this facility is in long-lived containers (e.g., stainless steel or galvanized drums), that have been tested to withstand the maximum expected load of a column of drums.
Licetise No SNM 778 Docket No.70-824 Date Ma rch, 1988 4
9 10-6 Amendment No.
Revision No.
Pm Babcock & Wilcox a McDermott company
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- 1. HEALTH PHYSICS
- 11. STORAGE POOL
- 2. PROCESS MET. LAB
- 12. ISOLATION AREA
- 3. HIGH TEMPERATURE LAB
- 13. HOT INSTRUMENT REPAIR
- 4. CERAMIC FORMING
- 14. EXPERIMENTAL ASSEMBLY AREA
- 5. COMMINUTION TECHNOLOGY
- 15. CASK HANDLING AREA
- 6. HEALTH PHYSICS
- 16. PRIMARY CELL (BASEMENT)
- 7. HOT CHANGE ROOM
- 17. if XPERIMENTAL POOL j
- 8. HEALTH PHYSICS
- 18. SAMPLE PREP. LAB l
9 LOOP SAMPLING ROOM
- 19. FAILURE ANALYSIS LAB l
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- 10. RADIOCHEMISTRY LAB
4 Revision No.
9 Page 10-15 l
l 880114036 / - b l Babcock & Wilcox l
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Fuel rods in any configuration or number, up to the number Q
in the assently, when limited to the confines of the assembly size are no more reactive than the intact assembly (Ref. Table 14-6).
14.3.2.6.5 Hot Cell Operations - Work within the hot cell will, by and large, follow existing controls.
Three units in addition to an assembly and its associated rod storage position are permitted within Cell No.1.
Two of the three units are restricted to rods confined within an ever safe cross sectional area, i.e., a cross sectional area not exceeding that of a 22.5 cm diameter cylinder; in additica these two units must be free draining of any water.
The third unit of Cell No.1 under mass control is permi tted. All other Hot Cells are limited to one unit each.
14.3.2.6.6 Fuel Rod Dismantlement - Fuel rods of either assembly type may be dismantled.
Dismantlement can be performed in any area which present licensing conditions permit fuel handling.
In addition, mass control must be limited to 350 grams of U-235, proper spacing must be maintained, and approved procedures must be followed.
14.3.2.6.7 Shipment and Disposal - The conditions of 4.2.2.7.7 are consis-tent with the above demonstration and/or current limits.
p 14.3.3 Outside Storage G
14.3.3.1 General - The underground storage and shipments are nuclearly isolated by distance or matter.
14.3.3.2 Underground Storage - The underground storage tubes are 5 inches in diameter, approximately 20 feet long and 20-inch centers.
Maximum units demonstrated safe in Section 14.3.2.2 are stored, one per tube.
These are neutronically isolated from each other by 15 inches of concrete.
14.3.4 Dry Waste Dry waste is waste that is free of liquids but not necessarily free of hydrogenous material.
Liquid waste which cannot be put through the hot drain system is solidified before disposal.
Nuclear Criti-cality Safety of dry waste is ensured by maintaining the concentra-tion of SNM to a value much less than an ever safe concentration.
Forty-five grams of SNM in a 30 gallon drum yields a concentration of less than 0.40 grams per liter.
By comparisor4, TID-7016 (Rev. 2)
License No SNM 778 Docket No. 70 824 Date March, 1988 4
9 14-16 Amendment No.
Revision No.
Page O
Babcock &Wilcox a McDermott company
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p reports the suberitical limit for fully enriched, optimumly moder-V ated U-235 to be 11.5 grams / liter and for Pu-239 the value is 7.0 grams / liter. The waste, as borne out by more than 20 years of experience, will maintain an approximate uniform distribution within the containers. Containers with unirradiated fuel are gamma scanned before transfer to verify that the maximum amount of SNM permitted per container (45 grams) is not exceeded. Assurance that containers with irradiated fuel do not exceed the maximum permitted amount of SNM is based on a mass balance difference.
The amount of SNM contained within irradiated fuel is specified by the customer when received.
Irradiated material is transferred into and out of units and hot cells based on the received value.
The difference between the amount of material transferred into a hot cell or unit and that transferred out of a hot cell or unit establishes the amount of SNM remaining in the hot cell or unit, in the fore, of con tamina tion.
Experience indicates that the contamination, which includes the SNM, is uniformly distributed in the waste.
There is therefore no requirment in the number or arrangement of containers within the radioactive waste building or in the temporary storage facili ty.
Even if the 45 grams of SNM were concentrated in the corrars of each container, the maximum amount of SNM at the inter-section of eight containers would be 360 grams of SNM and each 45 gram segment would be separated from the other by two thicknesses of steel.
Therefore, this is of no concern.
14.4 ANALYTICAL METHODS AND VALIDATION REFERENCES Nuclear criticality safety computer calculations presented in this chapter have used the computer codes NULIF, PDQ-07 and/or KENO.
The physi's codes NULIF and PDQ-07 are not only routinely used in nuclear criticclity safety to evaluate highly moderated low-enriched systems but also are the standard codes used by the reactor design group of the Babcock & Wilcox Company (both codes have been certified by the Company's Quality Assurance Program for reactor calculations).
The Monte Carlo code KENO is state-of-the-art in industry for nuclear criticality safety evaluations.
These three computer codes are des-cribed in Appendix A,Section III, pages 3 through 12 of SNM License No. 1168 (Docket 70-1201); validation for these codes are given in Appendix A Section III, of the same document on pages 19 through 21.
Future calculations for nuclear criticality safety will make use of these codes and the Nuclear Criticality Safety Codes in SCALE 3 (NITAWL-5, XSDRNPM-S, KENO-IVS and KENO-Ya).
SCALE 3 is described in NUREG/CR-0200.
Before use of the SCALE 3 package, the proper wording of the various codes will be assured and appropriate benchmarking activity will be carried out.
License No SNM 778 Docket No.70-824 Date March, 1988 4
Amendment No.
Revision No.
9 Page 14-17 Babcock & Wilcox a McDermott company
A 14.5 DATA SOURCES U
Data and Guidance for Nuclear Criticality Safety is taken from one or more of the sources specified below.
1.
Calculations using methods described in Section 14.4 2.
"Nuclear Safety Guide, TID-7016, Revision 2,"
NUREG/CR-0095 (ORNL/NUREG/CS0-6), (June, 1978.)
3.
"Nuclear Safety Guide, TID-7016 Revision 1," (1961).
TID-7016, Revision 1 is used only for application of the lattices density method which is Table IV and Figure 22 on page 26.
Table IY has been modified according to information published in the Federal Register, March 5,1963 on page 2130.
4.
American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Oxide Reactors, ANSI /ANS-8.1-1983).
5.
H. K. Clark, "Critical and Safe Masses and Dimensions of Lattices of U and UO Rods in Water" DP-1014, Savannah River Laboratory 2
(1966).
6.
H. C. Paxton, "Criticality Control in Operations with Fissile O
Material," LA-3366(Rev), Los Alamos Scientific Laboratory,
(
(1972).
7.
R. D. Carter, et al, "Criticality Handbook," ARH-600 Revised last November 6,1973, Atlantic Richfield Hanford Company, 14.6 FIXED POISONS 1
l The site does not now use Fixed Poisons to maintain nuclear criti-cality safety.
14.7 STRUCTURAL INTEGRITY Where structural integrity is necessary to provide assurance for j
nuclear criticality safety in any operation, the design and con-struction of those structures will be evaluated with due regard to i
load capacity and foreseeable abnornal loads, accidents tind deteri-oration.
This engineering activity is the responsibility of the Manager, Facilities with review and approval by a qualified person.
March, 1988 License No SNM 778 Docket No. 70 824 Date 4
9 14'18 Amendment No.
Revision No.
Page Babcock & Wilcox a McDermott company
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14.8 SPECIAL CONTROLS l
There are no special controls for nuclear criticality safety at the i
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