Potential Safety Issue Regarding the Shipment of Fissile MaterialML031050508 |
Person / Time |
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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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
12/06/1996 |
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From: |
Haughney C J NRC/NMSS/SFPO |
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To: |
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References |
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IN-96-063, NUDOCS 9612040215 |
Download: ML031050508 (9) |
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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 |
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Category:NRC Information Notice
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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 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
Addressees
All U.S. Nuclear Regulatory Commission licensees authorized to possess special nuclearmaterial in unsealed quantities greater than a critical mass.
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.
Description of Circumstances
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 case 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.gov
Attachments:
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 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.gov
Attachments:
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 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 Safeguards
Attachments:
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
- 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
>-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 Safeguards
Attachments:
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 Safeguards
Attachments:
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
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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)
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