KR-85 Hazards From Decayed Fuel| ML031130307 |
| 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, 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, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane |
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| Issue date: |
02/01/1990 |
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| Revision: |
0 |
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| From: |
Rossi C E Office of Nuclear Reactor Regulation |
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| To: |
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| References |
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| IN-90-008, NUDOCS 9001260198 |
| Download: ML031130307 (7) |
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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, 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, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane |
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Category:NRC Information Notice
[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 [[: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 [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>. |
UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555February 1. 1990NRC INFORMATION NOTICE NO. 90-08: KR-85 HAZARDS FROM DECAYED FUEL
Addressees
- All holders of operating licenses or construction permits for nuclear powerreactors and holders of licenses for permanently shutdown facilities withfuel on site.
Purpose
- This information notice alerts addressees to potential problems resulting from*the .accidental release of Kr-85 from decayed fuel. It is expected that recipients will review the Information for applicability to their facilities andconsider actions, as appropriate, to avoid similar problems. However, sugges-tions co'ntained in this information notice do not constitute NRC 'requirements;therefore, no specific action or written response is required.Desripionof Circumstances:During the licensing reviews for the Oconee independent spent fuel storageInstallation,, and in the decommissioning of the La Crosse and Dresden Unit 1power reactors, the NRC staff analyzed the radiological hazards associated.with the gases In decayed spent fuel. The age of the nuclear power industryand the lack of a permanent repository for spent fuel have resulted in theaccumulation of decayed'spent fuel.* Decayed spent fuel is manipulated afterlong shutdowns of operating reactors, during spent fuel pool re-racking, duringmo~vement to alternate reactor sites or independent spent fuel storage instal-lations, and during decommissioning. Analysis of hypothetical accidentsinvolving decayed spent fuel has focused attention on potential difficultiesthat'could be associated with the exposure of onsi1te personnel to an accidentalrelease of Kr-85. IKr-85 is a noble gas fission product that is present in thegaps between the fuel pellets and the cladding. It has a 10.76-year half-life,and, as a result of the considerably shorter half-lveso ital l tegaseous fission products (1-129 being the exception, but in low abundance),,Kr-85 becomes Increasingly the dominant nuclide in the accident source termfor gap releases as decay times increase. After 2 weeks of decay, Kr-85 isa significant nuclide in the source term, and after 190 days of decay, it isthe predominant gaseous nuclide for a gap release. The unusual decay character-istics of K~r-85 give cause for focusing attention on the onsite consequencesof a gap release from decayed fuel.,-9001260198 40--
IN 90-08February 1, 1990 Discussion:Kr-85 emits beta radiation with a maximum energy of 0.67 MeY for 99.6 percent ofthe decays and 0.51 MeV gamma radiation. for 0.4 percent of the decays. Conse-quently, direkt exposure to this gas would result in a dose to the skin approxi-mately 100 times the whole-body dose. Analysis of the relative consequences (interms of radiological doses) of a cask-drop accident as a function of decay timeof the fuel is illustrated in Figure 1. In the event of a serious accidentinvolving decayed spent fuel, protective actions would be needed for personnelon site, while offsite doses (assuming an exclusion area radius of 1 mile fromthe plant site) would be well below the Environmental Protection Agency'sProtective Action Guides. Accordingly, it is important to be able to properlysurvey and monitor for Kr-85, and to assess the skin dose to workers who couldbe exposed to Kr-85 in the event of an accident with decayed spent fuel.Licensees may wish to reevaluate whether Emergency Action Levels specified inthe emergency plan and procedures governing decayed fuel-handling, activitiesappropriately focus on concern for onsite workers and Kr-85 releases in areas'where decayed spent fuel accidents could occur, for example, the'spent fuelpool working floor. Furthermore, licensees may wish to determine if emergencyplans and corresponding implementing procedures address the means for limitingradiological exposures of onsite personnel who are in other areas of the plant.Among other things, moving onsite personnel away from the plume and shuttingoff building air intakes downwind from the source may be appropriate.This information notice requires no specific action or written response. If youhave any questions about the information in this notice, please contact one ofthe technical contacts listed below or the appropriate NRR project manager.Charles E. Ross Di ctorDivision'of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts: Charles S. Hinson, NRR(301) 492-3142Robert A. Meck, RES(301) 492-3737
Attachments:
1. Figure 1, Dose Consequences of aSpent Fuel Drop Accident2. List of Recently Issued NRC Information Notices N N..Atitchment 1IN 90-08 IFebruary 1, 1990 DOSE CONSEQUENCESOFA SPENTFUELDROPACCIDENT-103102ArMR SHUTDOWNFigure 1 Attachment 2in 90-08February 1, 1990Page I of ILIST OF RECENTLT ISSUEDNRC INFORMATION NOTICES}stanntinaV
- _Notice No.BJ-23,Supp. 2..I m ..-90-O7*90-0690-05 -90-0490-0390-0290-01_- --- 89-90 -_89-89SubjectPotential for Gas Binding.of Ngh-Prussura SsfetyInJection Pumps During aLoss-of-Coolant AccidentNew information RgardingInsulation Materal1Performance and DebrisBlockage of PWR Contain.ment SumpsPotential for Loss ofShutdown Cooling Whileat Low Reactor CoolantLevelsInter-Systes Discharge ofReactor CoolantCracking of the Upper Shell-to-TransitIon Cone 6irthWelds in Steam GeneratorsMalfunction of Borg-WarnerBolted Sonnet Check ValvesCaused by Failure of theSwing ArmPotential Degradation ofSecondary ContainsentImportance of ProperResponse to Self-IdentifledViolations by LicenseesPressurizr-Safty lLift Setpoint Shift.Eient NotificatinWorkshestsDate orIssuance1/31/901/30/90Issued toAll holders of OLsor CPs for PWRs.All holders of OLtsor CPs for nuclearpower reactors.1/29/90 All holders of OLsor CPs for nuclearpower reactors.1/29/901/26/901/23/90All holders of OLsor CPs for nuclearpower reactors.All holders'of OLsor CPs for Westinghouse-designed and CoatustionEngineering-designednuclear power reactors.All holders of OLsor CPs for nuclearpower reactors.1/22/90 All holders of OLs.or CPa for BWRs.1/12/90 All holders of NRCmaterials licenses.12t/28/81 All olbders or OLsor CPs for Prs.12/26/839 All holders of OLsor CPs for nuclearpower reactors:'OL
- Construction PermitUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555'!OFFICIAL BUSINESSPENALTY FOR PRIVATE USE. UOOIPOSTAGE It FEES PAIDIjusNAcj
-11 --1IN 90-08February 1, 1990 Discussion:Kr-85 emits beta radiation with a maximum energy of 0.67 MeY for 99.6 percent ofthe decays and 0.51 MeY gamma radiation for 0.4 percent of the decays. Conse-quently, direct exposure to this gas would result in a dose to the skin approxi-nately 100 times the whole-body dose. Analysis of the relative consequences (interms of radiological doses) of a cask-drop accident as a function of decay timeof the fuel is illustrated in Figure 1. In the event of a serious accidentinvolving decayed spent fuel, protective actions would be needed for personnelon site, while offsite doses (assuming an exclusion area radius of 1 mile fromthe plant site) would be well below the Environmental Protection Agency'sProtective Action Guides. Accordingly, it is important to be able to properlysurvey and monitor for Kr-85, and to assess the skin dose to workers who couldbe exposed to Kr-85 in the event of an accident with decayed spent fuel.Licensees may wish to reevaluate whether Emergency Action Levels specified inthe emergency plan and procedures governing decayed fuel-handling activitiesappropriately focus on concern for onsite workers and Kr-85 releases in areaswhere decayed spent fuel accidents could occur, for example, the spent fuelpool working floor. Furthermore, licensees may wish to determine if emergencyplans and corresponding implementing procedures address the means for limitingradiological exposures of onsite personnel who are in other areas of the plant.Among other things, moving onsite personnel away from the plume and shuttingoff building air intakes downwind from the source may be appropriate.This information notice requires no specific action or written response. If youhave any questions about the information in this notice, please contact one ofthe technical contacts listed below or the appropriate NRR project manager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts: Charles S. Hinson, NRR(301) 492-3142Robert A. Meck, RES(301) 492-3737
Attachments:
1. Figure 1, Dose Consequences of aSpent Fuel Drop Accident2. List of Recently Issued NRC Information Notices*See Previous ConcurrenceRPB:DREP SC:RPB:DREP SC:RPB:DREP DREP D:DREP RPB:ARM C/OG :DOEA:NRCSHinson* JEWigginton* LJCunningham* LCohen* FJCongel* TechEd* CHBerlinger*01/11/90 01/11/90 01/17/90 01/17/90 01/24/90 01/25/90 01/25/90D9/DOCUMENT NAME:INFORMATION NOTICE MECK ef r, .-IIN 90-XXJanuary xx, 1990 DISTRIBUTION:FJCongel I .9LJCunningham, NRRTHEssig, NRRJEWigginton, NRRRAErickson, NRRRJBarrett, NRRRLAnderson, TTCCSHinson, NRRLKCohen, NRRCHBerlinger, NRRCERossi, NRRCentral FilesRPB R/F*See Previous ConcurrenceRPB:DREPCSHInson*01/11/90SC:RPB:DREPJEWigginton*01/11/90SC:RPB:DREPLJCunnlnghal*01/17/90DREPLCohen*01/17/90D:DREPFJCongel*01/24/90RPB:ARMTechEd*01/25/90C/d@CB:DOEA:NRRCHBerlingerO1/jVi90D/DOEA:NRRCERossi01/ /90DOCUMENT NAME:INFORMATION NOTICE MECK
- *}. 'IN 90-XXJanuary xx, 1990 No specific action or written response is required by this information notice.If you have any questions about this matter, please contact one of the technicalcontacts listed below or the Regional Administrator of the appropriate regionaloffice.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical Contacts:Charles S. Hinson, NRR(301) 492-3142Robert A. Heck, RES(301) 492-3737
Attachments:
1.2.Figure 1List of Recently Issued NRC Information NoticesRPB:DREP SC lPJgBREPCSHinsoIMJ pginton01/ll /so ° /90D/DOEA:NRRCERossi01/ /904 Cu Ingham LCohen01/7/90 1/%A 190D:DRE 2 PB:MfFJConge Tol1zq/90 01&5/90onrC/OGCB:DOEA:NRRCHBerlinger01/ /90
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| list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Notice of Violation, Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Intergranular Stress Corrosion Cracking, Dissimilar Metal Weld, Exclusive Use)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990, Topic: Siren)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits, Stress corrosion cracking)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link, Siren)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990, Topic: Siren)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990, Topic: Loss of Offsite Power, Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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