|
|
Line 14: |
Line 14: |
| | page count = 9 | | | page count = 9 |
| }} | | }} |
| {{#Wiki_filter:K) JIM MCKNIGHTUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDSWASHINGTON, DC 20555December 5, 1996NRC INFORMATION NOTICE 96-63: POTENTIAL SAFETY ISSUE REGARDING THESHIPMENT OF FISSILE MATERIAL | | {{#Wiki_filter:K) JIM MCKNIGHT UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS=== |
| | WASHINGTON, DC 20555 December 5, 1996 NRC INFORMATION |
| | |
| | NOTICE 96-63: POTENTIAL |
| | |
| | SAFETY ISSUE REGARDING |
| | |
| | THE SHIPMENT OF FISSILE MATERIAL |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All U.S. Nuclear Regulatory Commission licensees authorized to possess special nuclearmaterial in unsealed quantities greater than a critical mass. | | All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | licensees |
| | |
| | authorized |
| | |
| | to possess special nuclear material in unsealed quantities |
| | |
| | greater than a critical mass. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alertaddressees to an issue with potential safety significance regarding shipments using the fissilematerial exemption provisions and general licenses. It is expected that recipients will review thisinformation for applicability to their facilities and consider actions, as appropriate, to avoid similarproblems. However, suggestions contained in this information notice are not NRC requirements;therefore, no specific action nor written response is required. | | The U.S. Nuclear Regulatory |
| | |
| | Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees |
| | |
| | to an issue with potential |
| | |
| | safety significance |
| | |
| | regarding |
| | |
| | shipments |
| | |
| | using the fissile material exemption |
| | |
| | provisions |
| | |
| | and general licenses. |
| | |
| | It is expected that recipients |
| | |
| | will review this information |
| | |
| | for applicability |
| | |
| | to their facilities |
| | |
| | and consider actions, as appropriate, to avoid similar problems. |
| | |
| | However, suggestions |
| | |
| | contained |
| | |
| | in this information |
| | |
| | notice are not NRC requirements; |
| | therefore, no specific action nor written response is required.Description |
| | |
| | of Circumstances |
| | |
| | An NRC licensee recently informed NRC of a potential |
| | |
| | situation |
| | |
| | where one of the fissile material exemptions |
| | |
| | in 10 CFR 71.53 would not have provided adequate criticality |
| | |
| | safety if large amounts of an exempt concentration |
| | |
| | of fissile material were to be transported |
| | |
| | in the presence of a special moderating |
| | |
| | material (i.e., beryllium). |
| | |
| | A recent contract was awarded to the licensee to process weapons-usable |
| | |
| | enriched uranium materials. |
| | |
| | The waste product, a uranium-beryllium |
| | |
| | filtercake, met the fissile exemption |
| | |
| | provisions |
| | |
| | in 10 CFR 71.53 and 49 CFR 173.453. The presence of beryllium |
| | |
| | in significant |
| | |
| | quantities |
| | |
| | in NRC-regulated |
| | |
| | fissile exempt shipments |
| | |
| | is extraordinary, and was not considered |
| | |
| | in the development |
| | |
| | of the fissile exemptions |
| | |
| | in the regulations. |
| | |
| | NRC has reviewed and verified the licensee's |
| | |
| | calculations, and has concluded |
| | |
| | that the current regulations |
| | |
| | need to be revised to preclude criticality |
| | |
| | in fissile exempt shipments |
| | |
| | made under 10 CFR 71.53, and fissile shipments |
| | |
| | made underthe general licenses in 10 CFR 71.18 and 10 CFR 71.22. This information |
| | |
| | notice is being issued to provide additional, timely notice, to licensees, of this potential |
| | |
| | safety issue, while the regulatory |
| | |
| | revisions |
| | |
| | are made.Discussion |
| | |
| | The licensee proposed to employ the provision |
| | |
| | in 10 CFR 71.53(d), or the parallel provision |
| | |
| | in the U.S. Department |
| | |
| | of Transportation (DOT) regulations, 49 CFR 173.453(d). |
| | |
| | J//1 961204021 on jl4Pqt PDR ETE OO~tc 99 IN 96-63 December 5, 1996 Section 71.53(d) exempts fissile material from the requirements |
| | |
| | in 10 CFR 71.55 and 71.59 (i.e., the additional |
| | |
| | requirements |
| | |
| | placed on fissile packages and shipments |
| | |
| | to preclude criticality), provided the package does not contain more than 5 grams (0.18 ounces) of fissile material in any 10-liter (610-cubic-inch) |
| | volume. The fissile exemptions |
| | |
| | appearing |
| | |
| | in 10 CFR 71.53 are assumed to provide inherent criticality |
| | |
| | control for all practical |
| | |
| | cases in which fissile materials exist at or below the applicable |
| | |
| | regulatory |
| | |
| | limits (i.e., independent |
| | |
| | calculations |
| | |
| | would generally not be expected nor required). |
| | |
| | Consequently, the fissile exemptions |
| | |
| | generally |
| | |
| | do not place limits on the types of moderating |
| | |
| | or reflecting |
| | |
| | material present in fissile exempt packages, nor the number of fissile exempt packages that can be shipped in a single consignment, and do not require that a transport |
| | |
| | index (see 10 CFR 71.4) be assigned to packages for criticality |
| | |
| | control.Further, the fissile material exemptions |
| | |
| | and general license provisions |
| | |
| | allow any licensee to make shipments |
| | |
| | without first seeking NRC approval.A fairly realistic |
| | |
| | computer model of the enriched uranium-beryllium |
| | |
| | oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated |
| | |
| | to provide adequate nuclear criticality |
| | |
| | safety. Because the current regulations |
| | |
| | would allow the possibility |
| | |
| | of criticality |
| | |
| | in fissile exempt shipments, and since there is no assurance |
| | |
| | that such shipments |
| | |
| | will not occur, NRC intends to revise 10 CFR Part 71 to address exclusion |
| | |
| | of beryllium |
| | |
| | and other special moderating |
| | |
| | material (e.g., deuterium |
| | |
| | and graphite) |
| | in the shipment of fissile materials, and to limit the amount of fissile exempt material that can be transported |
| | |
| | in a single consignment. |
| | |
| | NRC has contacted |
| | |
| | the U.S. Department |
| | |
| | of Energy (DOE) and the DOT on this issue. DOE is a shipper of fissile material, which could include the special moderating |
| | |
| | materials |
| | |
| | in question.NRC and DOT are coordinating |
| | |
| | the revisions |
| | |
| | to their respective |
| | |
| | regulations. |
| | |
| | NRC notes that very few licensees |
| | |
| | are involved in the shipment of fissile materials |
| | |
| | with beryllium, graphite, or deuterium. |
| | |
| | However, for those licensees |
| | |
| | that are involved in such shipments, it is important |
| | |
| | that programs be assessed to ensure that adequate criticality |
| | |
| | safety is provided where fissile materials |
| | |
| | are transported |
| | |
| | with materials |
| | |
| | known or expected to have moderating |
| | |
| | properties |
| | |
| | greater than water. As demonstrated |
| | |
| | by the licensee in this case, the existing fissile material exemptions |
| | |
| | cannot be presumed, without independent |
| | |
| | analysis, to preclude nuclear criticality |
| | |
| | in all cases. |
| | |
| | I):K,)IN 96-63 December 5, 1996 This information |
| | |
| | notice requires no specific action nor written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the individual |
| | |
| | listed below, or the appropriate |
| | |
| | NRC regional office.Charles J. Haighney, Actirt Dire Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards |
| | |
| | Technical |
| | |
| | contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov |
| | |
| | Attachments: |
| | 1. List of Recently Issued NMSS Information |
| | |
| | Notices 2. List of Recently Issued NRR Information |
| | |
| | Notices o k')~ Gu A 7- Attachment |
| | |
| | I IN 96-63 December 5, 1996 Page 1 of I LIST OF RECENTLY ISSUED NMSS INFORMATION |
| | |
| | NOTICES Info rmation Notice No.Date of Issuance Subject Issued to 96-57 96-54 96-53 Incident-Reporting |
| | |
| | Require-ments Involving |
| | |
| | Intakes, During a 24-Hour Period that May Cause a Total Effective |
| | |
| | ===Dose Equivalent=== |
| | in Excess of 0.05 Sv (5 rem)Vulnerability |
| | |
| | of Stainless Steel to Corrosion |
| | |
| | ===When Sensitized=== |
| | Retrofit to Amersham 660 Posilock Radiography |
| | |
| | Camera to Correct Incon-sistency in 10 CFR Part 34 Compatibility |
| | |
| | Cracked Insertion |
| | |
| | Rods on Troxler Model 3400 Series Portable Moisture Density Gauges Residual Contamination |
| | |
| | Remaining |
| | |
| | in Krypton-85 Handling System After Venting Recordkeeping, Decommis-sioning Notifications |
| | |
| | for Disposals |
| | |
| | of Radioactive |
| | |
| | Waste by Land Burial Authorized |
| | |
| | Under Former 10 CFR 20.304, 20.302, and Current 20.2002 10/30/96 10117/96 10/15/96 09/26/96 09/11/96 08/19196 All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | licensees All material licensees All industrial |
| | |
| | radiography |
| | |
| | licensees All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | portable gauge licensees |
| | |
| | and vendors All material licensees All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | licensees 96-52 96-51 96-47 v>Attachment |
| | |
| | 2 IN 96-63 December 5, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 96-62 96-61 96-60 96-59 96-58 Potential |
| | |
| | Failure of the Instantaneous |
| | |
| | Trip Function of General Electric RMS-9 Programmers |
| | |
| | Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly |
| | |
| | Installed |
| | |
| | Release Nut Potential |
| | |
| | Common-Mode |
| | |
| | Post-Accident Failure of Residual Heat Removal Heat Exchangers |
| | |
| | Potential |
| | |
| | Degradation |
| | |
| | of Post Loss-of-Coolant |
| | |
| | Recirculation |
| | |
| | Capability |
| | |
| | as a Result of Debris RCP Seal Replacement |
| | |
| | with Pump on Backseat Incident-Reporting |
| | |
| | Require-ments Involving |
| | |
| | Intakes, During a 24-Hour Period That May Cause a Total Effective |
| | |
| | ===Dose Equivalent=== |
| | in Excess of 0.05 Sv (5 rems)11/20/96 11/20/96 11/14/96 10/30/96 10/30/96 10/29/96 All holders of OLs and CPs for nuclear power plants All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for pressurized-water |
| | |
| | reactors All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | licensees 96-57 OL = Operating |
| | |
| | License CP = Construction |
| | |
| | Permit |
| | |
| | K>IN 96-63 v2 December 5, 1996 This information |
| | |
| | notice requires no specific action nor written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the individual |
| | |
| | listed below, or the appropriate |
| | |
| | NRC regional office.ChaSes J. Haugfey Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards |
| | |
| | Technical |
| | |
| | contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exeenrc.gov |
| | |
| | Attachments: |
| | 1. List of Recently Issued NMSS Information |
| | |
| | Notices 2. List of Recently Issued NRR Information |
| | |
| | Notices 96-63.IN*See Previous Concurrence. |
| | |
| | OFC SFPO* I c SFPO* l c SFPO* I c NRR/OECB* |
| | I c OGC* lc TEditor I NAME RLewis:LMG |
| | |
| | EEaston SShankman |
| | |
| | AEChaffee |
| | |
| | ENJenson EKraus*DATE 10/10/96 10/10/96 10/10/96 10/10/96 11/25/96 11/25/96 OFC lIMOB l I SFP t I I l- I NAME KRamsey CJH_ ney DATE 1/27/96 W215196 Ia; v4 i _ _C_ CO E E CO E N L S R O C C =COVER E = COVER & ENCLOSURE N = NE) CQPT |
| | |
| | IN 96-##KJ i2 October ##, 1996 present in fissile exempt packages, nor the number of fissile exempt packages that can be shipped in a single consignment, and do not require that a transport |
| | |
| | index (see 10 CFR 71.4) be assigned to packages for criticality |
| | |
| | control. Further, the fissile material exemptions |
| | |
| | and general license provisions |
| | |
| | allow any licensee to make shipments |
| | |
| | without first seeking NRC approval.A fairly realistic |
| | |
| | computer model of the enriched uranium-beryllium |
| | |
| | oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated |
| | |
| | to provide adequate nuclear criticality |
| | |
| | safety. Because the current regulations |
| | |
| | would allow the possibility |
| | |
| | of criticality |
| | |
| | in fissile exempt shipments, and since there is no assurance |
| | |
| | that such shipments |
| | |
| | will not occur, NRC intends to revise 10 CFR Part 71 to address exclusion |
| | |
| | of beryllium |
| | |
| | and other special moderating |
| | |
| | material (e.g., deuterium |
| | |
| | and graphite) |
| | in the shipment of fissile materials, and to limit the amount of fissile exempt material that can be transported |
| | |
| | in a single consignment. |
| | |
| | NRC has contacted |
| | |
| | the U.S. Department |
| | |
| | of Energy (DOE) and the DOT on this issue. DOE is a shipper of fissile material, which could include the special moderating |
| | |
| | materials |
| | |
| | in question. |
| | |
| | NRC and DOT are coordinating |
| | |
| | the revisions |
| | |
| | to their respective |
| | |
| | regulations. |
| | |
| | NRC notes that very few licensees |
| | |
| | are involved in the shipment of fissile materials-with |
| | |
| | beryllium, graphite, or deuterium. |
| | |
| | However, for those licensees |
| | |
| | that are involved in such shipments, it is important |
| | |
| | that programs be assessed to ensure that adequate criticality |
| | |
| | safety is provided where fissile materials |
| | |
| | are transported |
| | |
| | with materials |
| | |
| | known or expected to have moderating |
| | |
| | properties |
| | |
| | greater than water. As demonstrated |
| | |
| | by the licensee in this case, the existing fissile material exemptions |
| | |
| | cannot be presumed, without independent |
| | |
| | analysis, to preclude nuclear criticality |
| | |
| | in all cases.This information |
| | |
| | notice requires no specific action nor written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the individual |
| | |
| | listed below, or the appropriate |
| | |
| | NRC regional office.Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards |
| | |
| | Attachments: |
| | 1. List of Recently Issued NMSS Information |
| | |
| | Notices 2. List of Recently Issued NRR Information |
| | |
| | Notices Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov |
| | |
| | S:WPROJRXL1FIZ.IN |
| | |
| | See Previous Concurrence. |
| | |
| | OFC SFPON* c SFPO l c SFPO |
| | |
| | * c NRR/OECBh* |
| | I c OGCN lc TEditor I NAME RLewis:LMG |
| | |
| | EEaston SShankman |
| | |
| | AEChaffee |
| | |
| | ENJenson EKraus *DATE I 10/10/96 I 10/10/96 I 10/10/96 I 10/10/96 1 11/25/96 1 11/25/96 I--OFC IMOB I SFP lL,/ I l _NAME KRamseyeK |
| | |
| | CJHa_ _ _DATE 1I9 196 12- ?79 _6 _,,___. __ _ ________C -COVER E = COVER & LNULUbUKIt |
| | |
| | N = Nu iurO |
| | |
| | >-considerations |
| | |
| | and shipping experience |
| | |
| | indicate that the criticality |
| | |
| | of fissile exempt packages is not an immediate |
| | |
| | threat to worker and public health and safety, the possibility |
| | |
| | of criticality |
| | |
| | in fissile exempt shipments |
| | |
| | has prompted NRC to revise 10 CFR Part 71, to address the possible inclusion |
| | |
| | of beryllium |
| | |
| | and other special moderating |
| | |
| | material (e.g., deuterium |
| | |
| | and graphite) |
| | in the shipment of fissile materials, and to limit the amount of fissile exempt material which can be transported |
| | |
| | in a single consignment. |
| | |
| | NRC staff has also contacted |
| | |
| | the Department |
| | |
| | of Transportation (DOT) on this issue, as DOT regulations |
| | |
| | contain a parallel provision |
| | |
| | to 10 CFR 71.53 (i.e., 49 CFR 173.453).NRC and DOT are coordinating |
| | |
| | the revisions |
| | |
| | to their respective |
| | |
| | regulations. |
| | |
| | In practice, operating |
| | |
| | and administrative |
| | |
| | limits and procedures |
| | |
| | should prevent the collection |
| | |
| | of fissile materials |
| | |
| | in amounts or geometries |
| | |
| | which could achieve criticality |
| | |
| | as a result of any single change in the conditions |
| | |
| | necessary |
| | |
| | for criticality |
| | |
| | safety. Nevertheless, NRC notes that until the expedited |
| | |
| | regulatory |
| | |
| | revisions |
| | |
| | are made, good practice would be for licensees |
| | |
| | to exercise caution in deciding whether to ship: (1) fissile materials |
| | |
| | with materials |
| | |
| | known or expected to have moderating |
| | |
| | properties |
| | |
| | greater than water; or (2)single consignments |
| | |
| | of fissile exempt packages in excess of 290 grams of uranium-235 or 180 grams of other fissile radionuclides. |
| | |
| | As demonstrated |
| | |
| | by the licensee in this case, the existing fissile material exemptions |
| | |
| | cannot be presumed, without independent |
| | |
| | analysis, to preclude nuclear criticality |
| | |
| | in all cases.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below, or the appropriate |
| | |
| | NRC Regional Office.William D. Travers, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards |
| | |
| | Attachments: |
| | 1. List of Recently Issued NMSS Information |
| | |
| | Notices 2. List of Recently Issued NRR Information |
| | |
| | Notices Contact: Earl P. Easton, NMSS (301) 415-8527 S:IPROJIRXLFIZ.IN |
| | |
| | See Previous Concurrence. |
| | |
| | OFC lSFPO l -SFPO l f-0 e-O NRR/OECB l OGC l TEDITOR I NAME RLeg -sAG EEas aman b affee WReamer EKraus lATVS I J.JIIAIg -I -&.10 & I 0 I la;: I a lIda I I , -I I /on LO#% IV. I(V U l TO'I 1J1_IU 1 v IU Iva % I I I Ef %I OFC DWM I IMOB l SFPO I SFP NAME RJohnson KRamsey CJHaughney |
| | |
| | WDTravers DATE I/ /96 / /96 / /96 I /96 l C = COVER E = COVER & ENCLOSURE |
| | |
| | N = NO COPY 2 IN 96-##/ H October ##, 1996 shipped in a single consignment, and do not require that a transport |
| | |
| | index (see §71.4) be assigned to packages for criticality |
| | |
| | control. Further, the fissile material exemptions |
| | |
| | and general license provisions |
| | |
| | allow any licensee to make shipments |
| | |
| | without first seeking NRC approval.A fairly realistic |
| | |
| | computer model of the enriched uranium-beryllium |
| | |
| | oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated |
| | |
| | to provide adequate nuclear criticality |
| | |
| | safety. Because the current regulations |
| | |
| | would allow the possibility |
| | |
| | of criticality |
| | |
| | in fissile exempt shipments, and since there is no assurance |
| | |
| | that such shipments |
| | |
| | will not occur, NRC intends to revise 10 CFR Part 71, to address exclusion |
| | |
| | of beryllium |
| | |
| | and other special moderating |
| | |
| | material (e.g., deuterium |
| | |
| | and graphite) |
| | in the shipment of fissile materials, and to limit the amount of fissile exempt material which can be transported |
| | |
| | in a single consignment. |
| | |
| | NRC staff has contacted |
| | |
| | the U.S. Department |
| | |
| | of Energy (DOE) and the DOT on this issue.DOE is a shipper of fissile material, which could include the special moderating |
| | |
| | materials |
| | |
| | in question. |
| | |
| | NRC and DOT are coordinating |
| | |
| | the revisions |
| | |
| | to their respective |
| | |
| | regulations. |
| | |
| | NRC notes very few licensees |
| | |
| | are involved in the shipment of fissile materials |
| | |
| | with beryllium, graphite, or deuterium. |
| | |
| | However, for those licensees |
| | |
| | that are involved in such shipments, it is important |
| | |
| | that programs be assessed to ensure that adequate criticality |
| | |
| | safety is provided where fissile materials |
| | |
| | are transported |
| | |
| | with materials |
| | |
| | known or expected to have moderating |
| | |
| | properties |
| | |
| | greater than water. As demonstrated |
| | |
| | by the licensee in this case, the existing fissile material exemptions |
| | |
| | cannot be presumed, without independent |
| | |
| | analysis, to preclude nuclear criticality |
| | |
| | in all cases.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the individual |
| | |
| | listed below, or the appropriate |
| | |
| | NRC Regional Office.Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards |
| | |
| | Attachments: |
| | 1. List of Recently Issued NMSS Information |
| | |
| | Notices 2. List of Recently Issued NRR Information |
| | |
| | Notices Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov |
| | |
| | S:IPROJIRXLIFIZ.IN |
|
| |
|
| ==Description of Circumstances==
| | *See Previous Concurrence. |
| An NRC licensee recently informed NRC of a potential situation where one of the fissile materialexemptions in 10 CFR 71.53 would not have provided adequate criticality safety if large amountsof an exempt concentration of fissile material were to be transported in the presence of a specialmoderating material (i.e., beryllium). A recent contract was awarded to the licensee to processweapons-usable enriched uranium materials. The waste product, a uranium-beryllium filtercake,met the fissile exemption provisions in 10 CFR 71.53 and 49 CFR 173.453. The presence ofberyllium in significant quantities in NRC-regulated fissile exempt shipments is extraordinary, andwas not considered in the development of the fissile exemptions in the regulations. NRC hasreviewed and verified the licensee's calculations, and has concluded that the current regulationsneed to be revised to preclude criticality in fissile exempt shipments made under 10 CFR 71.53,and fissile shipments made underthe general licenses in 10 CFR 71.18 and 10 CFR 71.22. Thisinformation notice is being issued to provide additional, timely notice, to licensees, of thispotential safety issue, while the regulatory revisions are made.DiscussionThe licensee proposed to employ the provision in 10 CFR 71.53(d), or the parallel provision in theU.S. Department of Transportation (DOT) regulations, 49 CFR 173.453(d).J//1961204021 on jl4PqtPDR ETE OO~tc 99 IN 96-63December 5, 1996 Section 71.53(d) exempts fissile material from the requirements in 10 CFR 71.55 and 71.59 (i.e.,the additional requirements placed on fissile packages and shipments to preclude criticality),provided the package does not contain more than 5 grams (0.18 ounces) of fissile material inany 10-liter (610-cubic-inch) volume. The fissile exemptions appearing in 10 CFR 71.53 areassumed to provide inherent criticality control for all practical cases in which fissile materialsexist at or below the applicable regulatory limits (i.e., independent calculations would generallynot be expected nor required). Consequently, the fissile exemptions generally do not place limitson the types of moderating or reflecting material present in fissile exempt packages, nor thenumber of fissile exempt packages that can be shipped in a single consignment, and do notrequire that a transport index (see 10 CFR 71.4) be assigned to packages for criticality control.Further, the fissile material exemptions and general license provisions allow any licensee tomake shipments without first seeking NRC approval.A fairly realistic computer model of the enriched uranium-beryllium oxide waste packages, asloaded for shipment into a sea-land container, and at 0.5 grams per liter, could not bedemonstrated to provide adequate nuclear criticality safety. Because the current regulationswould allow the possibility of criticality in fissile exempt shipments, and since there is noassurance that such shipments will not occur, NRC intends to revise 10 CFR Part 71 to addressexclusion of beryllium and other special moderating material (e.g., deuterium and graphite) in theshipment of fissile materials, and to limit the amount of fissile exempt material that can betransported in a single consignment.NRC has contacted the U.S. Department of Energy (DOE) and the DOT on this issue. DOE is ashipper of fissile material, which could include the special moderating materials in question.NRC and DOT are coordinating the revisions to their respective regulations.NRC notes that very few licensees are involved in the shipment of fissile materials with beryllium,graphite, or deuterium. However, for those licensees that are involved in such shipments, it isimportant that programs be assessed to ensure that adequate criticality safety is provided wherefissile materials are transported with materials known or expected to have moderating propertiesgreater than water. As demonstrated by the licensee in this case, the existing fissile materialexemptions cannot be presumed, without independent analysis, to preclude nuclear criticality inall cases.
| |
|
| |
|
| I):K,)IN 96-63December 5, 1996 This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact the individual listed below, or theappropriate NRC regional office.Charles J. Haighney, Actirt DireSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsTechnical contact:Earl P. Easton, NMSS(301) 415-8520e-mail: exe@nrc.govAttachments:1. List of Recently Issued NMSS Information Notices2. List of Recently Issued NRR Information Noticeso k')~ Gu A 7- Attachment IIN 96-63December 5, 1996Page 1 of ILIST OF RECENTLY ISSUEDNMSS INFORMATION NOTICESInformationNotice No.Date ofIssuanceSubjectIssued to96-5796-5496-53Incident-Reporting Require-ments Involving Intakes,During a 24-Hour Periodthat May Cause a TotalEffective Dose Equivalentin Excess of 0.05 Sv (5 rem)Vulnerability of StainlessSteel to Corrosion WhenSensitizedRetrofit to Amersham 660Posilock RadiographyCamera to Correct Incon-sistency in 10 CFR Part 34CompatibilityCracked Insertion Rodson Troxler Model 3400Series Portable MoistureDensity GaugesResidual ContaminationRemaining in Krypton-85Handling System AfterVentingRecordkeeping, Decommis-sioning Notifications forDisposals of RadioactiveWaste by Land BurialAuthorized Under Former10 CFR 20.304, 20.302,and Current 20.200210/30/9610117/9610/15/9609/26/9609/11/9608/19196All U.S. Nuclear RegulatoryCommission licenseesAll material licenseesAll industrial radiographylicenseesAll U.S. Nuclear RegulatoryCommission portable gaugelicensees and vendorsAll material licenseesAll U.S. Nuclear RegulatoryCommission licensees96-5296-5196-47 v>Attachment 2IN 96-63December 5, 1996 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to96-6296-6196-6096-5996-58Potential Failure of theInstantaneous Trip Functionof General Electric RMS-9ProgrammersFailure of a Main Steam SafetyValve to Reseat Caused by anImproperly Installed ReleaseNutPotential Common-Mode Post-Accident Failure of ResidualHeat Removal Heat ExchangersPotential Degradation ofPost Loss-of-CoolantRecirculation Capabilityas a Result of DebrisRCP Seal Replacement withPump on BackseatIncident-Reporting Require-ments Involving Intakes,During a 24-Hour PeriodThat May Cause a TotalEffective Dose Equivalentin Excess of 0.05 Sv(5 rems)11/20/9611/20/9611/14/9610/30/9610/30/9610/29/96All holders of OLsand CPs for nuclearpower plantsAll holders of OLs orCPs for nuclear powerreactorsAll holders of OLs orCPs for nuclear powerreactorsAll holders of OLs orCPs for nuclear powerreactorsAll holders of OLs orCPs for pressurized-waterreactorsAll U.S. NuclearRegulatory Commissionlicensees96-57OL = Operating LicenseCP = Construction Permit | | OPP3 OFC SFPO* I c SFPO* lc SFPO* I c NRR/OECB* |
| | I c OG TE TOR I NAME RLewis:LMG |
|
| |
|
| K>IN 96-63v2 December 5, 1996 This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact the individual listed below, or theappropriate NRC regional office.ChaSes J. HaugfeyCharles J. Haughney, Acting DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsTechnical contact:Earl P. Easton, NMSS(301) 415-8520e-mail: exeenrc.govAttachments:1. List of Recently Issued NMSS Information Notices2. List of Recently Issued NRR Information Notices96-63.IN*See Previous Concurrence.OFC SFPO* I c SFPO* l c SFPO* I c NRR/OECB* I c OGC* lc TEditor INAME RLewis:LMG EEaston SShankman AEChaffee ENJenson EKraus*DATE10/10/9610/10/9610/10/9610/10/9611/25/9611/25/96OFC lIMOB l I SFP t I I l- INAME KRamsey CJH_ neyDATE 1/27/96 W215196 Ia; v4 i _ _C_ CO E E CO E N L S R O CC =COVERE = COVER & ENCLOSUREN = NE) CQPT
| | EEaston SShankman |
|
| |
|
| IN 96-##KJ i2 October ##, 1996 present in fissile exempt packages, nor the number of fissile exempt packages that can beshipped in a single consignment, and do not require that a transport index (see 10CFR 71.4) be assigned to packages for criticality control. Further, the fissile materialexemptions and general license provisions allow any licensee to make shipments withoutfirst seeking NRC approval.A fairly realistic computer model of the enriched uranium-beryllium oxide waste packages,as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not bedemonstrated to provide adequate nuclear criticality safety. Because the currentregulations would allow the possibility of criticality in fissile exempt shipments, and sincethere is no assurance that such shipments will not occur, NRC intends to revise 10CFR Part 71 to address exclusion of beryllium and other special moderating material (e.g.,deuterium and graphite) in the shipment of fissile materials, and to limit the amount offissile exempt material that can be transported in a single consignment.NRC has contacted the U.S. Department of Energy (DOE) and the DOT on this issue. DOEis a shipper of fissile material, which could include the special moderating materials inquestion. NRC and DOT are coordinating the revisions to their respective regulations.NRC notes that very few licensees are involved in the shipment of fissile materials-withberyllium, graphite, or deuterium. However, for those licensees that are involved in suchshipments, it is important that programs be assessed to ensure that adequate criticalitysafety is provided where fissile materials are transported with materials known or expectedto have moderating properties greater than water. As demonstrated by the licensee in thiscase, the existing fissile material exemptions cannot be presumed, without independentanalysis, to preclude nuclear criticality in all cases.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact the individual listed below, orthe appropriate NRC regional office.Charles J. Haughney, Acting DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsAttachments:1. List of Recently Issued NMSS Information Notices2. List of Recently Issued NRR Information NoticesContact: Earl P. Easton, NMSS(301) 415-8520e-mail: exe@nrc.govS:WPROJRXL1FIZ.IN See Previous Concurrence.OFC SFPON* c SFPO l c SFPO
| | AEChaffee |
|
| |
|
| * c NRR/OECBh* I c OGCN lc TEditor INAME RLewis:LMG EEaston SShankman AEChaffee ENJenson EKraus *DATE I 10/10/96 I 10/10/96 I 10/10/96 I 10/10/96 1 11/25/96 1 11/25/96I--OFC IMOB I SFP lL,/ I l _NAME KRamseyeK CJHa_ _ _DATE 1I9 196 12- ?79 _6 _,,___. __ _ ________C -COVERE = COVER & LNULUbUKItN = Nu iurO
| | _____enson |
|
| |
|
| >-considerations and shipping experience indicate that the criticality of fissile exemptpackages is not an immediate threat to worker and public health and safety, the possibilityof criticality in fissile exempt shipments has prompted NRC to revise 10 CFR Part 71, toaddress the possible inclusion of beryllium and other special moderating material (e.g.,deuterium and graphite) in the shipment of fissile materials, and to limit the amount offissile exempt material which can be transported in a single consignment.NRC staff has also contacted the Department of Transportation (DOT) on this issue, asDOT regulations contain a parallel provision to 10 CFR 71.53 (i.e., 49 CFR 173.453).NRC and DOT are coordinating the revisions to their respective regulations.In practice, operating and administrative limits and procedures should prevent thecollection of fissile materials in amounts or geometries which could achieve criticality as aresult of any single change in the conditions necessary for criticality safety. Nevertheless,NRC notes that until the expedited regulatory revisions are made, good practice would befor licensees to exercise caution in deciding whether to ship: (1) fissile materials withmaterials known or expected to have moderating properties greater than water; or (2)single consignments of fissile exempt packages in excess of 290 grams of uranium-235 or180 grams of other fissile radionuclides. As demonstrated by the licensee in this case, theexisting fissile material exemptions cannot be presumed, without independent analysis, topreclude nuclear criticality in all cases.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow, or the appropriate NRC Regional Office.William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsAttachments:1. List of Recently Issued NMSS Information Notices2. List of Recently Issued NRR Information NoticesContact: Earl P. Easton, NMSS(301) 415-8527S:IPROJIRXLFIZ.IN See Previous Concurrence.OFC lSFPO l -SFPO l f-0 e-O NRR/OECB l OGC l TEDITOR INAME RLeg -sAG EEas aman b affee WReamer EKrauslATVS I J.JIIAIg -I -&.10 & I 0 I la;: I a lIda I I , -I I /onLO#% IV. I(V U l TO'I 1J1_IU 1 v IU Iva % I I I Ef %IOFC DWM I IMOB l SFPO I SFPNAME RJohnson KRamsey CJHaughney WDTraversDATE I/ /96 / /96 / /96 I /96 lC = COVER E = COVER & ENCLOSURE N = NO COPY2 IN 96-##/ H October ##, 1996 shipped in a single consignment, and do not require that a transport index (see §71.4) beassigned to packages for criticality control. Further, the fissile material exemptions andgeneral license provisions allow any licensee to make shipments without first seeking NRCapproval.A fairly realistic computer model of the enriched uranium-beryllium oxide waste packages,as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not bedemonstrated to provide adequate nuclear criticality safety. Because the currentregulations would allow the possibility of criticality in fissile exempt shipments, and sincethere is no assurance that such shipments will not occur, NRC intends to revise10 CFR Part 71, to address exclusion of beryllium and other special moderating material(e.g., deuterium and graphite) in the shipment of fissile materials, and to limit the amountof fissile exempt material which can be transported in a single consignment.NRC staff has contacted the U.S. Department of Energy (DOE) and the DOT on this issue.DOE is a shipper of fissile material, which could include the special moderating materials inquestion. NRC and DOT are coordinating the revisions to their respective regulations.NRC notes very few licensees are involved in the shipment of fissile materials withberyllium, graphite, or deuterium. However, for those licensees that are involved in suchshipments, it is important that programs be assessed to ensure that adequate criticalitysafety is provided where fissile materials are transported with materials known or expectedto have moderating properties greater than water. As demonstrated by the licensee in thiscase, the existing fissile material exemptions cannot be presumed, without independentanalysis, to preclude nuclear criticality in all cases.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the individual listed below, orthe appropriate NRC Regional Office.Charles J. Haughney, Acting DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safetyand SafeguardsAttachments:1. List of Recently Issued NMSS Information Notices2. List of Recently Issued NRR Information NoticesContact: Earl P. Easton, NMSS(301) 415-8520e-mail: exe@nrc.govS:IPROJIRXLIFIZ.IN *See Previous Concurrence. OPP3OFC SFPO* I c SFPO* lc SFPO* I c NRR/OECB* I c OG TE TOR INAME RLewis:LMG EEaston SShankman AEChaffee _____enson EKrausDATE I /196 / /96 1 1/96 I /196 1 196 I /196OFC DWM I IMOB l FlO I Sl FPO I jINAME RJohnson KRamsey CJHaughney WDTraversDATE I/ /96 I /96 1 /196 / /96 J .I.. ==_C = COVERE = COVER & ENCLOSUREN = NU COPlY
| | EKraus DATE I /196 / /96 1 1/96 I /196 1 196 I /196 OFC DWM I IMOB l FlO I Sl FPO I jI NAME RJohnson KRamsey CJHaughney |
|
| |
|
| }} | | WDTravers DATE I/ /96 I /96 1 /196 / /96 J .I.. ==_C = COVER E = COVER & ENCLOSURE N = NU COPlY}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Potential Safety Issue Regarding the Shipment of Fissile MaterialML031050508 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
12/06/1996 |
---|
From: |
Haughney C J NRC/NMSS/SFPO |
---|
To: |
|
---|
References |
---|
IN-96-063, NUDOCS 9612040215 |
Download: ML031050508 (9) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
K) JIM MCKNIGHT UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, DC 20555 December 5, 1996 NRC INFORMATION
NOTICE 96-63: POTENTIAL
SAFETY ISSUE REGARDING
THE SHIPMENT OF FISSILE MATERIAL
Addressees
All U.S. Nuclear Regulatory
Commission
licensees
authorized
to possess special nuclear material in unsealed quantities
greater than a critical mass.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to an issue with potential
safety significance
regarding
shipments
using the fissile material exemption
provisions
and general licenses.
It is expected that recipients
will review this information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action nor written response is required.Description
of Circumstances
An NRC licensee recently informed NRC of a potential
situation
where one of the fissile material exemptions
in 10 CFR 71.53 would not have provided adequate criticality
safety if large amounts of an exempt concentration
of fissile material were to be transported
in the presence of a special moderating
material (i.e., beryllium).
A recent contract was awarded to the licensee to process weapons-usable
enriched uranium materials.
The waste product, a uranium-beryllium
filtercake, met the fissile exemption
provisions
in 10 CFR 71.53 and 49 CFR 173.453. The presence of beryllium
in significant
quantities
in NRC-regulated
fissile exempt shipments
is extraordinary, and was not considered
in the development
of the fissile exemptions
in the regulations.
NRC has reviewed and verified the licensee's
calculations, and has concluded
that the current regulations
need to be revised to preclude criticality
in fissile exempt shipments
made under 10 CFR 71.53, and fissile shipments
made underthe general licenses in 10 CFR 71.18 and 10 CFR 71.22. This information
notice is being issued to provide additional, timely notice, to licensees, of this potential
safety issue, while the regulatory
revisions
are made.Discussion
The licensee proposed to employ the provision
in 10 CFR 71.53(d), or the parallel provision
in the U.S. Department
of Transportation (DOT) regulations, 49 CFR 173.453(d).
J//1 961204021 on jl4Pqt PDR ETE OO~tc 99 IN 96-63 December 5, 1996 Section 71.53(d) exempts fissile material from the requirements
in 10 CFR 71.55 and 71.59 (i.e., the additional
requirements
placed on fissile packages and shipments
to preclude criticality), provided the package does not contain more than 5 grams (0.18 ounces) of fissile material in any 10-liter (610-cubic-inch)
volume. The fissile exemptions
appearing
in 10 CFR 71.53 are assumed to provide inherent criticality
control for all practical
cases in which fissile materials exist at or below the applicable
regulatory
limits (i.e., independent
calculations
would generally not be expected nor required).
Consequently, the fissile exemptions
generally
do not place limits on the types of moderating
or reflecting
material present in fissile exempt packages, nor the number of fissile exempt packages that can be shipped in a single consignment, and do not require that a transport
index (see 10 CFR 71.4) be assigned to packages for criticality
control.Further, the fissile material exemptions
and general license provisions
allow any licensee to make shipments
without first seeking NRC approval.A fairly realistic
computer model of the enriched uranium-beryllium
oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated
to provide adequate nuclear criticality
safety. Because the current regulations
would allow the possibility
of criticality
in fissile exempt shipments, and since there is no assurance
that such shipments
will not occur, NRC intends to revise 10 CFR Part 71 to address exclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material that can be transported
in a single consignment.
NRC has contacted
the U.S. Department
of Energy (DOE) and the DOT on this issue. DOE is a shipper of fissile material, which could include the special moderating
materials
in question.NRC and DOT are coordinating
the revisions
to their respective
regulations.
NRC notes that very few licensees
are involved in the shipment of fissile materials
with beryllium, graphite, or deuterium.
However, for those licensees
that are involved in such shipments, it is important
that programs be assessed to ensure that adequate criticality
safety is provided where fissile materials
are transported
with materials
known or expected to have moderating
properties
greater than water. As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.
I):K,)IN 96-63 December 5, 1996 This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC regional office.Charles J. Haighney, Actirt Dire Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Technical
contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices o k')~ Gu A 7- Attachment
I IN 96-63 December 5, 1996 Page 1 of I LIST OF RECENTLY ISSUED NMSS INFORMATION
NOTICES Info rmation Notice No.Date of Issuance Subject Issued to 96-57 96-54 96-53 Incident-Reporting
Require-ments Involving
Intakes, During a 24-Hour Period that May Cause a Total Effective
Dose Equivalent
in Excess of 0.05 Sv (5 rem)Vulnerability
of Stainless Steel to Corrosion
When Sensitized
Retrofit to Amersham 660 Posilock Radiography
Camera to Correct Incon-sistency in 10 CFR Part 34 Compatibility
Cracked Insertion
Rods on Troxler Model 3400 Series Portable Moisture Density Gauges Residual Contamination
Remaining
in Krypton-85 Handling System After Venting Recordkeeping, Decommis-sioning Notifications
for Disposals
of Radioactive
Waste by Land Burial Authorized
Under Former 10 CFR 20.304, 20.302, and Current 20.2002 10/30/96 10117/96 10/15/96 09/26/96 09/11/96 08/19196 All U.S. Nuclear Regulatory
Commission
licensees All material licensees All industrial
radiography
licensees All U.S. Nuclear Regulatory
Commission
portable gauge licensees
and vendors All material licensees All U.S. Nuclear Regulatory
Commission
licensees 96-52 96-51 96-47 v>Attachment
2 IN 96-63 December 5, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 96-62 96-61 96-60 96-59 96-58 Potential
Failure of the Instantaneous
Trip Function of General Electric RMS-9 Programmers
Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly
Installed
Release Nut Potential
Common-Mode
Post-Accident Failure of Residual Heat Removal Heat Exchangers
Potential
Degradation
of Post Loss-of-Coolant
Recirculation
Capability
as a Result of Debris RCP Seal Replacement
with Pump on Backseat Incident-Reporting
Require-ments Involving
Intakes, During a 24-Hour Period That May Cause a Total Effective
Dose Equivalent
in Excess of 0.05 Sv (5 rems)11/20/96 11/20/96 11/14/96 10/30/96 10/30/96 10/29/96 All holders of OLs and CPs for nuclear power plants All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for pressurized-water
reactors All U.S. Nuclear Regulatory
Commission
licensees 96-57 OL = Operating
License CP = Construction
Permit
K>IN 96-63 v2 December 5, 1996 This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC regional office.ChaSes J. Haugfey Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Technical
contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exeenrc.gov
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices 96-63.IN*See Previous Concurrence.
OFC SFPO* I c SFPO* l c SFPO* I c NRR/OECB*
I c OGC* lc TEditor I NAME RLewis:LMG
EEaston SShankman
AEChaffee
ENJenson EKraus*DATE 10/10/96 10/10/96 10/10/96 10/10/96 11/25/96 11/25/96 OFC lIMOB l I SFP t I I l- I NAME KRamsey CJH_ ney DATE 1/27/96 W215196 Ia; v4 i _ _C_ CO E E CO E N L S R O C C =COVER E = COVER & ENCLOSURE N = NE) CQPT
IN 96-##KJ i2 October ##, 1996 present in fissile exempt packages, nor the number of fissile exempt packages that can be shipped in a single consignment, and do not require that a transport
index (see 10 CFR 71.4) be assigned to packages for criticality
control. Further, the fissile material exemptions
and general license provisions
allow any licensee to make shipments
without first seeking NRC approval.A fairly realistic
computer model of the enriched uranium-beryllium
oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated
to provide adequate nuclear criticality
safety. Because the current regulations
would allow the possibility
of criticality
in fissile exempt shipments, and since there is no assurance
that such shipments
will not occur, NRC intends to revise 10 CFR Part 71 to address exclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material that can be transported
in a single consignment.
NRC has contacted
the U.S. Department
of Energy (DOE) and the DOT on this issue. DOE is a shipper of fissile material, which could include the special moderating
materials
in question.
NRC and DOT are coordinating
the revisions
to their respective
regulations.
NRC notes that very few licensees
are involved in the shipment of fissile materials-with
beryllium, graphite, or deuterium.
However, for those licensees
that are involved in such shipments, it is important
that programs be assessed to ensure that adequate criticality
safety is provided where fissile materials
are transported
with materials
known or expected to have moderating
properties
greater than water. As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC regional office.Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov
S:WPROJRXL1FIZ.IN
See Previous Concurrence.
OFC SFPON* c SFPO l c SFPO
I c OGCN lc TEditor I NAME RLewis:LMG
EEaston SShankman
AEChaffee
ENJenson EKraus *DATE I 10/10/96 I 10/10/96 I 10/10/96 I 10/10/96 1 11/25/96 1 11/25/96 I--OFC IMOB I SFP lL,/ I l _NAME KRamseyeK
CJHa_ _ _DATE 1I9 196 12- ?79 _6 _,,___. __ _ ________C -COVER E = COVER & LNULUbUKIt
N = Nu iurO
>-considerations
and shipping experience
indicate that the criticality
of fissile exempt packages is not an immediate
threat to worker and public health and safety, the possibility
of criticality
in fissile exempt shipments
has prompted NRC to revise 10 CFR Part 71, to address the possible inclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material which can be transported
in a single consignment.
NRC staff has also contacted
the Department
of Transportation (DOT) on this issue, as DOT regulations
contain a parallel provision
to 10 CFR 71.53 (i.e., 49 CFR 173.453).NRC and DOT are coordinating
the revisions
to their respective
regulations.
In practice, operating
and administrative
limits and procedures
should prevent the collection
of fissile materials
in amounts or geometries
which could achieve criticality
as a result of any single change in the conditions
necessary
for criticality
safety. Nevertheless, NRC notes that until the expedited
regulatory
revisions
are made, good practice would be for licensees
to exercise caution in deciding whether to ship: (1) fissile materials
with materials
known or expected to have moderating
properties
greater than water; or (2)single consignments
of fissile exempt packages in excess of 290 grams of uranium-235 or 180 grams of other fissile radionuclides.
As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below, or the appropriate
NRC Regional Office.William D. Travers, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices Contact: Earl P. Easton, NMSS (301) 415-8527 S:IPROJIRXLFIZ.IN
See Previous Concurrence.
OFC lSFPO l -SFPO l f-0 e-O NRR/OECB l OGC l TEDITOR I NAME RLeg -sAG EEas aman b affee WReamer EKraus lATVS I J.JIIAIg -I -&.10 & I 0 I la;: I a lIda I I , -I I /on LO#% IV. I(V U l TO'I 1J1_IU 1 v IU Iva % I I I Ef %I OFC DWM I IMOB l SFPO I SFP NAME RJohnson KRamsey CJHaughney
WDTravers DATE I/ /96 / /96 / /96 I /96 l C = COVER E = COVER & ENCLOSURE
N = NO COPY 2 IN 96-##/ H October ##, 1996 shipped in a single consignment, and do not require that a transport
index (see §71.4) be assigned to packages for criticality
control. Further, the fissile material exemptions
and general license provisions
allow any licensee to make shipments
without first seeking NRC approval.A fairly realistic
computer model of the enriched uranium-beryllium
oxide waste packages, as loaded for shipment into a sea-land container, and at 0.5 grams per liter, could not be demonstrated
to provide adequate nuclear criticality
safety. Because the current regulations
would allow the possibility
of criticality
in fissile exempt shipments, and since there is no assurance
that such shipments
will not occur, NRC intends to revise 10 CFR Part 71, to address exclusion
of beryllium
and other special moderating
material (e.g., deuterium
and graphite)
in the shipment of fissile materials, and to limit the amount of fissile exempt material which can be transported
in a single consignment.
NRC staff has contacted
the U.S. Department
of Energy (DOE) and the DOT on this issue.DOE is a shipper of fissile material, which could include the special moderating
materials
in question.
NRC and DOT are coordinating
the revisions
to their respective
regulations.
NRC notes very few licensees
are involved in the shipment of fissile materials
with beryllium, graphite, or deuterium.
However, for those licensees
that are involved in such shipments, it is important
that programs be assessed to ensure that adequate criticality
safety is provided where fissile materials
are transported
with materials
known or expected to have moderating
properties
greater than water. As demonstrated
by the licensee in this case, the existing fissile material exemptions
cannot be presumed, without independent
analysis, to preclude nuclear criticality
in all cases.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the individual
listed below, or the appropriate
NRC Regional Office.Charles J. Haughney, Acting Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRR Information
Notices Contact: Earl P. Easton, NMSS (301) 415-8520 e-mail: exe@nrc.gov
S:IPROJIRXLIFIZ.IN
- See Previous Concurrence.
OPP3 OFC SFPO* I c SFPO* lc SFPO* I c NRR/OECB*
I c OG TE TOR I NAME RLewis:LMG
EEaston SShankman
AEChaffee
_____enson
EKraus DATE I /196 / /96 1 1/96 I /196 1 196 I /196 OFC DWM I IMOB l FlO I Sl FPO I jI NAME RJohnson KRamsey CJHaughney
WDTravers DATE I/ /96 I /96 1 /196 / /96 J .I.. ==_C = COVER E = COVER & ENCLOSURE N = NU COPlY
|
---|
|
list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
... further results |
---|