ML20246M271

Application for Renewal of License SNM-1227

ML20246M271
Person / Time
Site:	Framatome ANP Richland
Issue date:	08/22/1989
From:	SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
To:	Rouse L NRC
References
NUDOCS 8909070126
Download: ML20246M271 (8)

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14. /,2f7 ADEMCEIDNUCLEARFUELSCORPORATION fpg CONTROLLED DOCUMENT TRANSMITTAL / RECEIPT FOR CONTROLLED OFF-SITE DISTRIBUTION Date: August 22, 1989 To:

USNRC/LC Rouse (6) From: DOCUMENT CONTROL ADVANCED NUCLEAR FUELS CORPORATION 2101 HORN RAPIDS ROAD RICHLAND, WA 99352 DOCUMENT NUMBER: ANF-2 REVISION NUMBER: la COPY NUMBER: n/a DOCUMENT TITLE: APPLICATION FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE NO SNrt-1227 (NRC DOCKET NO. 70-1257) Please acknowledge receipt vv Please destroy obsolete copies or pages Please enter approved revisions Other Receipt of the above is hereby acknowledged. Required entries have been made and obsolete information has been destroyed / returned.

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Date PLEASE SIGN AND RETURN THIS SHEET TO*. DOCUMENT CONTROL ADVANCED NUCLEAR FUELS CORPORATION 2101 HORN RAPIDS ROAD RICHLAND, WA 99352 / 8909070126 890822 '{ -{DR ADOCK0700g7 ANF-3145 305 A (7/8 ) adnf"f

).> I 1 PAGE OF DOCUMENT REVISION INSTRUCTION SHEET I DOCUMENT NUMBER: ANF-2 NRC LICENSE DOCUMENT TITLE: i l

l DOCUMENT REVISION:

19 IDENTIFICATION REMOVE INSERT (1.E., SPECI FICATION, DRAWING, PROCEDU RE, ETC.) PAGE(S) REVISION PAGE(S) REVISION Amendment #4 19 Chapter 1 1-2 13 1-2 19 1-3 13 1-3 19 l-4 13 1-4 19 Chapter 8 8-1 13 8-1 19 Distribution 18 19 q e IF THE SPECIFICATIONS OR PAGES ARE ONLY REMOVED AND NOT REPLACED, PLACE DASHES IN THE INSERT COLUMNS. e IF THE SPECIFICATION 5 OR PAGES ARE ONLY ADDITIONS (NO REPLACEMENTS), PLACE DASHES IN THE REMOVE COLUMNS. ANF-3145.498A (12,S8)

.,m ,y i -?; ANF-2, Rev. 19 Issue Date:.8/22/89 APPLICATION FOR RENEWAL OF. ~ - SPECIAL NUCLEAR MATERIAL. LICENSE NO. SNM-1227 (NRC DOCKET N0. 70-1257) a DISTRIBUTION L. A. Bisping-T. A. Bjernard-B. N. Femreite E. L. Foster R. G.-Frain-C. J. Francis J. W. Fredericks L. D. Gerrald [. J. L. Glesener A W. V. Jackson D. C. Kilian-D. C. Lehfeldt C. W. Malody T. W. Patten J. E. Pieper-T. C. Probasco.(4) G. L. Ritter I. J. Samaritano L. J. Sevigny J. R. Singleton W. E. Stavig i. I. J. Urza l N. A. Vaught C.'J. Volmer USNRC/L. C. Rouse (6) DSHS/G. Robertson (2) Document Control (5) O Ib__m__m m.___ _ _ _ _ __m__ .___._.m.m_

L + A@fANCED Nt) CLEAR FUELS CORPORATION XN-2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM-1227, NRC DOCKET NO. 70-1257 ( PARI I - LICENSE CONDITIONS $( CHAPTER *i STANDARD CONDITIONS AND SPECIAL AUTHORIZATIONS 1.1 Corporate Information The name of the applicant is Advanced Nuclear Fuels Corporation (ANF). The applicant is a corporation incorporated in the State of Delaware with its principal corporate offices located at 600108th Avenue N.E., Bellevue, Washington 98009. Applicant is a wholly-owned subsidiary-of Siemens KWU, Inc., a Delaware Corporation that is a wholly-owned subsidiary of Siemens Capital Corporation, a Delaware corporation with headquarters in f.ew York City. Siemens Capital Corporation is in turn wholly-owned by Siemens AG headquartered in Munich, Federal Republic of Germany. The fuels fabrication plant for which this application is being made is located at 2101 Horn Rapids Road, Richland, Washington 99352. 1.2 Site Location The fuels fabrication facility is located in the State of Washing-ton, County of Benton, City of Richland. It is sited on a 320 acre tract, 0.9 miles west of the intersection of Stevens Drive and Horn [N Rapids Road within the north boundary of the City of Richland. The sit e Q is on the south side of Horn Rapids Road which provides access. All activities with special nuclear materials are conducted within a controlled access area. The processing of uranium compounds is conducted primarily within the UO2 and Speciality fuels (SF) facilities with some development activity or pilot scale work in the Engineering Laboratory. Liquid waste processing is conducted primarily in the ammonia recovery facility and lagoon uranitsn recovery facility which are sited within the waste storage lagoon area. Solid waste is packaged in the various facilities and stored in containers in designated storage areas while awaiting shipment to a low level radioactive waste disposal site or incineration of the combustible waste in the SF Building. Storage of various uranium compounds is conducted in the various production facil-ities or in the Packaged Radioactive Materials Warehouse and Materials Warehouse. Storage of UF6 cylinders is conducted outside 07 pads adjacent to the U0 l 2 P ant and packaged fuel elements or other uranitrn products are stored outside or in a warehouse while awaiting shipment. 1.3 License Number and Period of License 1.3.1 Special Nuclear Materials License This application is for renewal of Special Nuclear Material License No. SNM-1227 (NRC Docket No. 70-1257). The current license expires on p October 31, 1986 and renewal is requested to cover a period of five (5) V years. AMENDMENT APPLICATION DATE: November 12, 1987 PAGE NO.: j_1 XN-NFf01422 (2/87)

l AMANCEDNUCLEARFUELSCORPORATION .g.g SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 O PART I - LICENSE CONDITIONS

agy, 19 1.4 Possession Limits 1.4.1 Uranium-235 l

1 One hundred grams, in addition to the' limits listed below, of any enrichment or form for analytical purposes. 2. Nine and one-half kilograms contained in uranium compounds enriched from 10.00 wt% to a maximum of 19.99 wt% in the U-235 isotope (see Section 1.6.2 for restrictions). 3. Two hundrcd kilograms contained in uranium compounds enriched from 5.00 wt% to a maximum of 9.99 wt% in the U-235 isotope (see Section 1.6.2 for restrictions). 4. Twenty thousand kilograms contained in uranium compounds in any form enriched to a maximum of 5 wt% in the U-235 isotope. 1.4.2 Plutonium (<500 aramst 1. One milligram and not mor'e than 1.5 millicuries as contained in I sealed sources and standards. f 2. Less than 500 grams as Pu02 or Pu0 -U02 as stored waste. 2 1.5 Authorized Activities Specific locations of authorized activities involving special nu. clear materials are identified in Table 1-1.1. I 1.6 Exemotigm and Special Authorizations 1.6.1 Criticality Accident Alarm System Exemotion Pursuant to 10 CFR 70.24(d), Advanced Nuclear Fuels has previously requested exemption in part from the requirements of 10 CFR 70.24(a), and has been duly authorized to use the criticality accident alarm system described below in its facilities. In addition, the waste storage lagoons have been exempted from coverage by the criticality accident alarm system. The criticality accident alarm system used in the Advanced Nuclear Fuels facilities employs neutron criticality detectors (NCDs), which are operated in two-cut-of-a (where n = 3 to 6 per comparator panel) . coincidence to minimize the possibility of spurious trips due to NCD malfunction or response to radiation other than neutror:s characteristic-of a criticality accident. WE*tOMENT A#PUCATION DATE. ~ ' PAGE NO.: April 1, 1989 1-2 ANF 3830C*AA ($g3)

7_ q a y AD%SNCEDNUCLEARFUELSCORPORATION y._, SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM.1227, NRC DOCKET NO. 701257 DO PART I - LICENSE CONDITIONS 19 The Advanced Nuclear Fueis criticality accident alarm system l consists of NCDs, comparator units, associated control

panels, an annunciator panel, and howlers.

'Each comparator unit is capable of monitoring the failure and trip signals of up to six NCDs. Each NCD consists of a BF3 tube (externally moderated) with associated pulse amplifiers, trip circuits, performance audit circuits, and associated power supplies. Failure audit circuits check the operation of each BF3 tube, pulse amplifier, multivibrator, and low and high voltage supplies by requiring a minimum background count rate of 100 counts per minute. This background count rate is provided by an internal radiation source in each BF3 tube. If the minimum background is not detected by the audit circuit, a failure (indicating malfunction) is signaled. Such failure signals do not interfere with operation of the criticality accident alarm system. Because the trip circuitry is not audited, redundant trip circuits o are provided in each NCD. Failure and trip signals from all NCDs are fed ij to comparator units. Redundant trip detection is provided in the k comparator units. The comparator panels display all failure and trip signals. When two or more NCDs connected to the same comparator unit are tripped, the criticality accident alarm (howlers) is activated. An annunciator unit monitors the status of the comparator units, and an audible alarm is actuated in the Central Guard Station in the event that the annunciator unit detects either a failure or trip signal. The minimum detectable criticality burst width for the Advanced Nuclear Fuels criticality accident alarm system is 50 microseconds. An overall system reliability test is conducted quarterly. The trip point of each NCD is set to trip within 1-5 seconds at 80 mrem /hr (fast neutrons). The neutron dose rate delivered throegh 12 inches of concrete to an 4 NCD at 300 feet as a remit of a minimum burst of 10 fissions (taken as the minimum criticality accident which must be detectable) has been calculated to be approximately 350 mrem /hr. Except for the waste lagoons which have been exempted from coverage by the criticality accident alarm system, all special nuclear material at the Advanced Nuclear fuels plant shall be located such that a pN) AMENDMENT APP!JCATiON DATE. PAGE NO: ANF 383L1051 A (5/88) _an__________________._

ADVANCEDNUCLEARFLELSCORPORATION gn'g.g ~ SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 1227, NRC DOCKET NO. 701257 O PART I - LICENSE CONDITIONS g, 19 criticality accident of 1014 fissions occurring in the material would produce a minimum of 350 mrem /hr at a set of three NCDs, considering distance and intervening shielding materials. 1.6.2 Special Processino of Uranium Enriched From 5 to 19.99 wt% U-235 Uranium compounds enriched in the U-235 iso' tope in excess of 5 wt%, but not exceeding 19.99 wt%, may be received, stored, processed and transferred. All License Conditions described in this application shall apply to the handling, processing and si.iragc of these materials. However, in addition, the Special Conditions described below shall also apply. 1.6.2.1 Receiot and Storace These materials shall be received on-site and stored in containers distinctly different (e.g., size, color) from those routinely uscd for uranium enriched in the U-235 isotope to less than or equal to 5 wt%. Containers of these materials, including scrap and contaminated solid wastes, shall be labeled identifying' the enrichment and form, and shall be stored separate from (not commingled with) uranium enriched in the U-235 isotope to less than or equal to 5 wt%. 1.6.2.2 Processina These materials shall be handled and processed on a safe batch (less than or equal to 45% of the minimum critical mass) basis, and each processing station shall be limited to an inventory of one safe batch, regardless of material form, unless it is demonstrated that: 1. Existing equipment and/or vessels to be used are shown to be I adequately subcritical, for the special enrichment uranium to be processed, in accordance with criticality safety analysis methods described in the License Conditions; or l 2. Existing equipment and/or vessels can be appropriately modified i or replaced to conform to criticality limits, for the special enrichment uranium to be processed, established in accordance with criticality safety methods described in the License l Conditions. l In all cases, appropriate labels shall be located with the material to identify it as special enrichment uranium. These materials shall be segregated from other fissile materials throughout the process. l AMENDMENT APPUCATION DATE: PAGE NO.: Aprii 1, 1989 1-4 ANF.3830 051 A $88) h

l .+ _ ' EDifANCEDNUCLEARFUELSCORPORATION g p.2 SPECIAL NUCLEAR MATERIAL LICENSE NO. SNM 12-27, NRC DOCKET NO. 701257 gs RT I - LICENSE CONDITIONS g,y, 19 CHAPTER 8 RADIOLOGICAL CONTINGENCY PLAH Advanced Nuclear Fuels developed and published a radiological contingency plan as document ANF-32, Part I entitled, " Advanced Nuclear Fuels Corporation Richland Fuels Fabrication Pla.nt Emergency Plan, Part I, The Plan." The lhtest revision to the plan was issued on January 31, 1989. The licensee shall maintain implementing procedures for the plan. In addition, the licensee shall make no change in the plan, without the approval of the Commission, if the change would decrease the effectiveness of the plan. The licensee may make changes to the plan provided the changes do not decrease the effectiveness of the plan. In addition, the licensee shall provide a description of each change to the Chief, Fuel Cycle Safety Branch, within six months after each change is made. C AMENOMENT APPUCATION DATE. PAGE NO: April 1, 1989 B-1 ANF 230.051A (5886 _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}