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| ==Description of Circumstances== | | ==Description of Circumstances== |
| The recent retrofit to the safety latch plate (NRC Information Notice 97-35, dated June 18,1997), which corrected a scenario where the INC Model IR100 radiography camera would notpass the horizontal shock test, as required by 10 CFR 34.20, resulted in the equipment notmeeting the requirement that the lock should not be easily removed by unauthorized personnel.INC and the State of California evaluated the problem, and INC took action to correct thesituation.DiscusionThe "Safety Latch Plate" on the IR100 radiography camera has a potentially more "fragile areas(as specified in ANSI N432-1980, Paragraph 8.3.2) than the area previously tested.Apparently, if the Safety Latch Plate was struck directly on the front surface of the plate (withthe source in the safe locked position), the plate could be deformed and deemed inoperable. Italso appeared that the plate might be susceptible to damage if struck from the top and side. Toensure that this type of potential damage was not possible, a bumper that would prevent9¢ ho ROTOR- q1og 0 rlal_ asd 64thaf %9120901 1i'.1 b ([12 -f /,c IN 97-87December 12,1997 deformation was welded to the back of the Safety Latch Plate, and the outer top edge of the platewas angled at a 45-to-50-degree angle, to a depth of approximately 3 mm (0.12 inch). Themodified device was tested to ensure compliance with ANSI N432-1980, paragraph 8.2.In the Safety Latch plate retrofit to the IR1 00, the Allen screws used to fasten the plate to thedevice were such that they were easily removed by the user. This is contrary to requirements in10 CFR 34.20(a) which states that all devices in use meet the requirements of ANSI N432-1980.ANSI N432, Section 5.1.2.1, requires that 0(t]he exposure device shall have a lock which is noteasily removable by unauthorized personnel." To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tamperinq ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment I contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Licensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.\.9Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical contacts: David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS301415-5868E-mail: mlb5@nrc.gov | | The recent retrofit to the safety latch plate (NRC Information Notice 97-35, dated June 18,1997), which corrected a scenario where the INC Model IR100 radiography camera would notpass the horizontal shock test, as required by 10 CFR 34.20, resulted in the equipment notmeeting the requirement that the lock should not be easily removed by unauthorized personnel.INC and the State of California evaluated the problem, and INC took action to correct thesituation.DiscusionThe "Safety Latch Plate" on the IR100 radiography camera has a potentially more "fragile areas(as specified in ANSI N432-1980, Paragraph 8.3.2) than the area previously tested.Apparently, if the Safety Latch Plate was struck directly on the front surface of the plate (withthe source in the safe locked position), the plate could be deformed and deemed inoperable. Italso appeared that the plate might be susceptible to damage if struck from the top and side. Toensure that this type of potential damage was not possible, a bumper that would prevent9¢ ho ROTOR- q1og 0 rlal_ asd 64thaf %9120901 1i'.1 b ([12 -f /,c |
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| | IN 97-87December 12,1997 deformation was welded to the back of the Safety Latch Plate, and the outer top edge of the platewas angled at a 45-to-50-degree angle, to a depth of approximately 3 mm (0.12 inch). Themodified device was tested to ensure compliance with ANSI N432-1980, paragraph 8.2.In the Safety Latch plate retrofit to the IR1 00, the Allen screws used to fasten the plate to thedevice were such that they were easily removed by the user. This is contrary to requirements in10 CFR 34.20(a) which states that all devices in use meet the requirements of ANSI N432-1980.ANSI N432, Section 5.1.2.1, requires that 0(t]he exposure device shall have a lock which is noteasily removable by unauthorized personnel." To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tamperinq ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment I contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Licensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.\.9Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical contacts: David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS301415-5868E-mail: mlb5@nrc.govAttachments: /V" g ke1. INC Retrofit Letter2. List of Recently Issued NMSS Information Notices3. List of Recently Issued NRC Information Notices |
| /V" g ke1. INC Retrofit Letter2. List of Recently Issued NMSS Information Notices3. List of Recently Issued NRC Information Notices IIN 97-87December 12, 1997 IsIiiIINDUSTRLAL NUCLEAR CCO K'c.OCTOBER 24, 1§97SUBJECT; IR- 00 EXPOSURE DEVICE LQCK.DEAR CUSTOMERiACCORDING TO I 17 CC 30332(C)(1) AND ANSI N432-1980,5.1.2.1, EACH IOGRkpHIC DEVICE MUAT HAVE A LOCK THAT IS NOTEASILY BMA3 BY UNAUTOIZE PRSONNEL. IN OTHER WORDSONLY KNOWLED LE OR AUTHORIZED PtRSONNEL SHOULD DISMANTLETHE LOCK ASSE BLY.TO rNSURE THEI ABOVE REGULATION, INC WILL INSTALL A HEAVYDUTY FOI LABL OVER T ALLEN SCREW ON THE LOCK BOX (RIGHTSIDE OLY) TS LABEL WILL STATE "tO BE REMOVED ONLY BYAUTHORIZED PESONNEL.INC WILL INSTALL THE LABELS FREE OF CHARGE ON EVERY DEVICESHIPPED TO US! FOR RELOADING OR MAIOTAINENCE. IF WE DO NOTRECIEvE YOUR DEVICE WITHIN f'o DAYS !FROM THE ABOVE DATE, WEWILL SEND YOU' THE LABELS FOR YOU TO INSTALL.THANK YOU FOA YOUR CONTINUED SUPPORT. IF YOU HAVE ANY QUESTIONSPLEASE CALL ipic AT 1-800-711-1962.VERY TRULY YOURS.S.A .UDDLE ON '''I., II IBh& _ u~ Len. CAWCAMOCE:14220 Waksw4 (510) as.o.-T^l 0 ^-
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| "Sclment 2IN 97-87December 12, 1997 LIST OF RECENTLY ISSUEDNMSS INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-8697-7597-7297-6597-6497-6197-5897-57Additional Controls for Transportof the Amersham Model No. 660Series Radiographic ExposureDevicesEnforcement Sanctions Issuedas a Result of DeliberateViolations of NRC RequirementsPotential for Failureof the Omega SeriesSprinkler HeadsFailures of High-Dose-Rate Remote AfterloadingDevice Source Guide Tubes,Catheters, and ApplicatorsPotential ProblemsAssociated with Lossof Electrical Powerin Certain TeletherapyUnitsU.S. Department ofHealth and HumanServices Letter, toMedical Device Manu-facturers, on theYear 2000 ProblemMechanical Integrity ofIn-Situ Leach InjectionWells and PipingLeak Testing of PackagingUsed in the Transport ofRadioactive Material12/12/9709/24/9709/22/9708/15/9708/13/9708/06/9707/31/9707/30/97Registered users of the ModelNo. 660 series packages, andNuclear Regulatory Commissionindustrial radiography licenseesAll U.S. Nuclear RegulatoryCommission licenseesAll holders of OLs or CPsfor nuclear power reactorsand fuel cycle facilitiesAll high-dose-rate remoteafterloader licenseesAll U.S. Nuclear RegulatoryCommission medical tele-therapy licenseesAll U.S. Nuclear RegulatoryCommission medicallicensees, veterinarians,and manufacturers/distri-butors of medical devicesHolders of and Applicantsfor Licenses for In-SituLeach FacilitiesSuppliers and users ofpackaging for the trans-portation of radioactivematerial required to per-form packaging leak tests Attachment 3IN 97-87December 12, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-8697-8597-8495-49,Sup. 197-8397-82Additional Controls forTransport of the AmershamModel No. 660 SeriesRadiographic Exposure DevicesEffects of Crud Buildupand Boron Deposition onPower Distribution andShutdown MarginRupture in ExtractionSteam Piping as aResult of Flow-AcceleratedCorrosionSeismic Adequacy ofThermo-Lag PanelsRecent Events InvolvingReactor Coolant SystemInventory Control DuringShutdownInadvertent Control RoomHalon Actuation Due to aCamera Flash12/12/9712/11/9712/11/9712/10/9712/05/9711/28/97Registered users of the ModelNo. 660 series packages, andNuclear Regulatory Commissionindustrial radiography licenseesAll holders of OLs for pressurized-water reactors, except thoselicensees who have permanentlyceased operations and havecertified that the fuel has beenpermanently removed from thereactor vesselAll holders of OLs for nuclearpower reactors except thosewho have permanently ceasedoperations and have certifiedthat fuel has been permanentlyremoved from the reactor vesselAll holders of OLs for nuclearpower reactorsAll holders of OLs for pressurized-water reactors, except thoselicensees who have permanentlyceased operations and havecertified that fuel has beenpermanently removed from thereactor vesselAll holders of OLs for nuclearpower reactorsOL = Operating LicenseCP = Construction Permit J ~IN 97-xxK~Novembe;r1997 easily removable by unauthorized personnel.! To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tampering ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment 1 contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Ucensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical Contacts:David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS(301) 415-5868E-mail: mlb5@nrc.gov
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| | IIN 97-87December 12, 1997 IsIiiIINDUSTRLAL NUCLEAR CCO K'c.OCTOBER 24, 1§97SUBJECT; IR- 00 EXPOSURE DEVICE LQCK.DEAR CUSTOMERiACCORDING TO I 17 CC 30332(C)(1) AND ANSI N432-1980,5.1.2.1, EACH IOGRkpHIC DEVICE MUAT HAVE A LOCK THAT IS NOTEASILY BMA3 BY UNAUTOIZE PRSONNEL. IN OTHER WORDSONLY KNOWLED LE OR AUTHORIZED PtRSONNEL SHOULD DISMANTLETHE LOCK ASSE BLY.TO rNSURE THEI ABOVE REGULATION, INC WILL INSTALL A HEAVYDUTY FOI LABL OVER T ALLEN SCREW ON THE LOCK BOX (RIGHTSIDE OLY) TS LABEL WILL STATE "tO BE REMOVED ONLY BYAUTHORIZED PESONNEL.INC WILL INSTALL THE LABELS FREE OF CHARGE ON EVERY DEVICESHIPPED TO US! FOR RELOADING OR MAIOTAINENCE. IF WE DO NOTRECIEvE YOUR DEVICE WITHIN f'o DAYS !FROM THE ABOVE DATE, WEWILL SEND YOU' THE LABELS FOR YOU TO INSTALL.THANK YOU FOA YOUR CONTINUED SUPPORT. IF YOU HAVE ANY QUESTIONSPLEASE CALL ipic AT 1-800-711-1962.VERY TRULY YOURS.S.A .UDDLE ON '''I., II IBh& _ u~ Len. CAWCAMOCE:14220 Waksw4 (510) as.o.-T^l 0 ^- |
| 1. INC retrofit letter2. Lst of Recently Issued NRC Information Notices3 List of Recently Issued NMSS Information NoticesDistribution:SSSS r/F NE02-SSD-3 KRamsey, IMOBCoordinated with State of California iejDOCUMENT NAME: A:\JR100lN.IN EKraus via fax 10/24197receive a copy of this document, Indicate In the box: v | | "Sclment 2IN 97-87December 12, 1997 LIST OF RECENTLY ISSUEDNMSS INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-8697-7597-7297-6597-6497-6197-5897-57Additional Controls for Transportof the Amersham Model No. 660Series Radiographic ExposureDevicesEnforcement Sanctions Issuedas a Result of DeliberateViolations of NRC RequirementsPotential for Failureof the Omega SeriesSprinkler HeadsFailures of High-Dose-Rate Remote AfterloadingDevice Source Guide Tubes,Catheters, and ApplicatorsPotential ProblemsAssociated with Lossof Electrical Powerin Certain TeletherapyUnitsU.S. Department ofHealth and HumanServices Letter, toMedical Device Manu-facturers, on theYear 2000 ProblemMechanical Integrity ofIn-Situ Leach InjectionWells and PipingLeak Testing of PackagingUsed in the Transport ofRadioactive Material12/12/9709/24/9709/22/9708/15/9708/13/9708/06/9707/31/9707/30/97Registered users of the ModelNo. 660 series packages, andNuclear Regulatory Commissionindustrial radiography licenseesAll U.S. Nuclear RegulatoryCommission licenseesAll holders of OLs or CPsfor nuclear power reactorsand fuel cycle facilitiesAll high-dose-rate remoteafterloader licenseesAll U.S. Nuclear RegulatoryCommission medical tele-therapy licenseesAll U.S. Nuclear RegulatoryCommission medicallicensees, veterinarians,and manufacturers/distri-butors of medical devicesHolders of and Applicantsfor Licenses for In-SituLeach FacilitiesSuppliers and users ofpackaging for the trans-portation of radioactivematerial required to per-form packaging leak tests |
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| | Attachment 3IN 97-87December 12, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-8697-8597-8495-49,Sup. 197-8397-82Additional Controls forTransport of the AmershamModel No. 660 SeriesRadiographic Exposure DevicesEffects of Crud Buildupand Boron Deposition onPower Distribution andShutdown MarginRupture in ExtractionSteam Piping as aResult of Flow-AcceleratedCorrosionSeismic Adequacy ofThermo-Lag PanelsRecent Events InvolvingReactor Coolant SystemInventory Control DuringShutdownInadvertent Control RoomHalon Actuation Due to aCamera Flash12/12/9712/11/9712/11/9712/10/9712/05/9711/28/97Registered users of the ModelNo. 660 series packages, andNuclear Regulatory Commissionindustrial radiography licenseesAll holders of OLs for pressurized-water reactors, except thoselicensees who have permanentlyceased operations and havecertified that the fuel has beenpermanently removed from thereactor vesselAll holders of OLs for nuclearpower reactors except thosewho have permanently ceasedoperations and have certifiedthat fuel has been permanentlyremoved from the reactor vesselAll holders of OLs for nuclearpower reactorsAll holders of OLs for pressurized-water reactors, except thoselicensees who have permanentlyceased operations and havecertified that fuel has beenpermanently removed from thereactor vesselAll holders of OLs for nuclearpower reactorsOL = Operating LicenseCP = Construction Permit |
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| | J ~IN 97-xxK~Novembe;r1997 easily removable by unauthorized personnel.! To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tampering ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment 1 contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Ucensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical Contacts:David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS(301) 415-5868E-mail: mlb5@nrc.govAttachments:1. INC retrofit letter2. Lst of Recently Issued NRC Information Notices3 List of Recently Issued NMSS Information NoticesDistribution:SSSS r/F NE02-SSD-3 KRamsey, IMOBCoordinated with State of California iejDOCUMENT NAME: A:\JR100lN.IN EKraus via fax 10/24197receive a copy of this document, Indicate In the box: v |
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| * Copy wthout at'advemnenedosure v *Copy wlth attadmeenclosure NW No copyNOFFICE IMAB gIMAB i<Im IMA?3 e WMSK D IMi d DCi NAME IMABurgess A nd3aggefB I-CaBer M.icc iM DC%. lDATE 1,2 I Of /97 | | * Copy wthout at'advemnenedosure v *Copy wlth attadmeenclosure NW No copyNOFFICE IMAB gIMAB i<Im IMA?3 e WMSK D IMi d DCi NAME IMABurgess A nd3aggefB I-CaBer M.icc iM DC%. lDATE 1,2 I Of /97 |
| * I /97 /2/f1 /97 ho1J /97 '// 7OFFICIAL RECORD COPY IN 97-.?November\wpr 97 easily removable by unauthorized personnel." To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tampering ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment 1 contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Licensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical Contacts: David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS(301) 415-5868E-mail: mlb5@nrc.gov | | * I /97 /2/f1 /97 ho1J /97 '// 7OFFICIAL RECORD COPY |
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| | IN 97-.?November\wpr 97 easily removable by unauthorized personnel." To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tampering ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment 1 contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Licensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical Contacts: David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS(301) 415-5868E-mail: mlb5@nrc.govAttachments:1. INC retrofit letter2. List of Recently Issued NRC Information Notices3. List of Recently Issued NMSS Information NoticesDistribution:SSSS rH NE02-SSD-3 KRamsey, IMOBCoordinated with State of California PX-aDOCUMENT NAME: A:iR100N.IN EKraus via fax 10124197To recelve a copy of this document, Indicate I the box: 'C" a Copy w thout attachmentenclosure "E" |
| | * Copy with atachment/endosure AND m No copyl OFFICE IMAB m IMAB I IMAB 'n0- 1 IMORt\ IMPS W 14% LNAME MMBurgesslmb 1SBaggett LCamper IJPiqw 1DC4 //DATE /,2 / Oe /97 7 Y 7 /97 12f 9 1- /97 I-i/ r-\47OFFICIAL RECORD COPY |
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| 1. INC retrofit letter2. List of Recently Issued NRC Information Notices3. List of Recently Issued NMSS Information NoticesDistribution:SSSS rH NE02-SSD-3 KRamsey, IMOBCoordinated with State of California PX-aDOCUMENT NAME: A:iR100N.IN EKraus via fax 10124197To recelve a copy of this document, Indicate I the box: 'C" a Copy w thout attachmentenclosure "E"
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| * Copy with atachment/endosure AND m No copyl OFFICE IMAB m IMAB I IMAB 'n0- 1 IMORt\ IMPS W 14% LNAME MMBurgesslmb 1SBaggett LCamper IJPiqw 1DC4 //DATE /,2 / Oe /97 7 Y 7 /97 12f 9 1- /97 I-i/ r-\47OFFICIAL RECORD COPY}}
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Second Retrofit to Industrial Nuclear Company IR100 Radiography Camera, to Correct Inconsistency in 10 CFR Part 34 CompatibilityML031050023 |
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: |
12/12/1997 |
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From: |
Cool D A NRC/NMSS/IMNS |
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To: |
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References |
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IN-97-087, NUDOCS 9712090210 |
Download: ML031050023 (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, 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
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>. |
UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDSWASHINGTON, DC 20555December 12, 1997NRC INFORMATION NOTICE 97-87: SECOND RETROFIT TO INDUSTRIAL NUCLEARCOMPANY IRiOO RADIOGRAPHY CAMERA, TOCORRECT INCONSISTENCY IN 10 CFR PART 34COMPATIBILITY
Addressees
All industrial radiography licensees.PuMroseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to makelicensees aware of a retrofit to the lock of the Industrial Nuclear Company (INC) Model IR100Radiography Camera, to correct an inconsistency in 10 CFR Part 34 compatibility. It isexpected that recipients will review the information for applicability to their licensed activities,and consider actions, as appropriate, to avoid problems. However, suggestions contained inthis information notice are not NRC requirements; therefore, no specific action nor writtenresponse is required.
Description of Circumstances
The recent retrofit to the safety latch plate (NRC Information Notice 97-35, dated June 18,1997), which corrected a scenario where the INC Model IR100 radiography camera would notpass the horizontal shock test, as required by 10 CFR 34.20, resulted in the equipment notmeeting the requirement that the lock should not be easily removed by unauthorized personnel.INC and the State of California evaluated the problem, and INC took action to correct thesituation.DiscusionThe "Safety Latch Plate" on the IR100 radiography camera has a potentially more "fragile areas(as specified in ANSI N432-1980, Paragraph 8.3.2) than the area previously tested.Apparently, if the Safety Latch Plate was struck directly on the front surface of the plate (withthe source in the safe locked position), the plate could be deformed and deemed inoperable. Italso appeared that the plate might be susceptible to damage if struck from the top and side. Toensure that this type of potential damage was not possible, a bumper that would prevent9¢ ho ROTOR- q1og 0 rlal_ asd 64thaf %9120901 1i'.1 b ([12 -f /,c
IN 97-87December 12,1997 deformation was welded to the back of the Safety Latch Plate, and the outer top edge of the platewas angled at a 45-to-50-degree angle, to a depth of approximately 3 mm (0.12 inch). Themodified device was tested to ensure compliance with ANSI N432-1980, paragraph 8.2.In the Safety Latch plate retrofit to the IR1 00, the Allen screws used to fasten the plate to thedevice were such that they were easily removed by the user. This is contrary to requirements in10 CFR 34.20(a) which states that all devices in use meet the requirements of ANSI N432-1980.ANSI N432, Section 5.1.2.1, requires that 0(t]he exposure device shall have a lock which is noteasily removable by unauthorized personnel." To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tamperinq ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment I contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Licensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.\.9Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical contacts: David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS301415-5868E-mail: mlb5@nrc.govAttachments: /V" g ke1. INC Retrofit Letter2. List of Recently Issued NMSS Information Notices3. List of Recently Issued NRC Information Notices
IIN 97-87December 12, 1997 IsIiiIINDUSTRLAL NUCLEAR CCO K'c.OCTOBER 24, 1§97SUBJECT; IR- 00 EXPOSURE DEVICE LQCK.DEAR CUSTOMERiACCORDING TO I 17 CC 30332(C)(1) AND ANSI N432-1980,5.1.2.1, EACH IOGRkpHIC DEVICE MUAT HAVE A LOCK THAT IS NOTEASILY BMA3 BY UNAUTOIZE PRSONNEL. IN OTHER WORDSONLY KNOWLED LE OR AUTHORIZED PtRSONNEL SHOULD DISMANTLETHE LOCK ASSE BLY.TO rNSURE THEI ABOVE REGULATION, INC WILL INSTALL A HEAVYDUTY FOI LABL OVER T ALLEN SCREW ON THE LOCK BOX (RIGHTSIDE OLY) TS LABEL WILL STATE "tO BE REMOVED ONLY BYAUTHORIZED PESONNEL.INC WILL INSTALL THE LABELS FREE OF CHARGE ON EVERY DEVICESHIPPED TO US! FOR RELOADING OR MAIOTAINENCE. IF WE DO NOTRECIEvE YOUR DEVICE WITHIN f'o DAYS !FROM THE ABOVE DATE, WEWILL SEND YOU' THE LABELS FOR YOU TO INSTALL.THANK YOU FOA YOUR CONTINUED SUPPORT. IF YOU HAVE ANY QUESTIONSPLEASE CALL ipic AT 1-800-711-1962.VERY TRULY YOURS.S.A .UDDLE ON I., II IBh& _ u~ Len. CAWCAMOCE:14220 Waksw4 (510) as.o.-T^l 0 ^-
"Sclment 2IN 97-87December 12, 1997 LIST OF RECENTLY ISSUEDNMSS INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-8697-7597-7297-6597-6497-6197-5897-57Additional Controls for Transportof the Amersham Model No. 660Series Radiographic ExposureDevicesEnforcement Sanctions Issuedas a Result of DeliberateViolations of NRC RequirementsPotential for Failureof the Omega SeriesSprinkler HeadsFailures of High-Dose-Rate Remote AfterloadingDevice Source Guide Tubes,Catheters, and ApplicatorsPotential ProblemsAssociated with Lossof Electrical Powerin Certain TeletherapyUnitsU.S. Department ofHealth and HumanServices Letter, toMedical Device Manu-facturers, on theYear 2000 ProblemMechanical Integrity ofIn-Situ Leach InjectionWells and PipingLeak Testing of PackagingUsed in the Transport ofRadioactive Material12/12/9709/24/9709/22/9708/15/9708/13/9708/06/9707/31/9707/30/97Registered users of the ModelNo. 660 series packages, andNuclear Regulatory Commissionindustrial radiography licenseesAll U.S. Nuclear RegulatoryCommission licenseesAll holders of OLs or CPsfor nuclear power reactorsand fuel cycle facilitiesAll high-dose-rate remoteafterloader licenseesAll U.S. Nuclear RegulatoryCommission medical tele-therapy licenseesAll U.S. Nuclear RegulatoryCommission medicallicensees, veterinarians,and manufacturers/distri-butors of medical devicesHolders of and Applicantsfor Licenses for In-SituLeach FacilitiesSuppliers and users ofpackaging for the trans-portation of radioactivematerial required to per-form packaging leak tests
Attachment 3IN 97-87December 12, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-8697-8597-8495-49,Sup. 197-8397-82Additional Controls forTransport of the AmershamModel No. 660 SeriesRadiographic Exposure DevicesEffects of Crud Buildupand Boron Deposition onPower Distribution andShutdown MarginRupture in ExtractionSteam Piping as aResult of Flow-AcceleratedCorrosionSeismic Adequacy ofThermo-Lag PanelsRecent Events InvolvingReactor Coolant SystemInventory Control DuringShutdownInadvertent Control RoomHalon Actuation Due to aCamera Flash12/12/9712/11/9712/11/9712/10/9712/05/9711/28/97Registered users of the ModelNo. 660 series packages, andNuclear Regulatory Commissionindustrial radiography licenseesAll holders of OLs for pressurized-water reactors, except thoselicensees who have permanentlyceased operations and havecertified that the fuel has beenpermanently removed from thereactor vesselAll holders of OLs for nuclearpower reactors except thosewho have permanently ceasedoperations and have certifiedthat fuel has been permanentlyremoved from the reactor vesselAll holders of OLs for nuclearpower reactorsAll holders of OLs for pressurized-water reactors, except thoselicensees who have permanentlyceased operations and havecertified that fuel has beenpermanently removed from thereactor vesselAll holders of OLs for nuclearpower reactorsOL = Operating LicenseCP = Construction Permit
J ~IN 97-xxK~Novembe;r1997 easily removable by unauthorized personnel.! To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tampering ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment 1 contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Ucensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical Contacts:David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS(301) 415-5868E-mail: mlb5@nrc.govAttachments:1. INC retrofit letter2. Lst of Recently Issued NRC Information Notices3 List of Recently Issued NMSS Information NoticesDistribution:SSSS r/F NE02-SSD-3 KRamsey, IMOBCoordinated with State of California iejDOCUMENT NAME: A:\JR100lN.IN EKraus via fax 10/24197receive a copy of this document, Indicate In the box: v
- Copy wthout at'advemnenedosure v *Copy wlth attadmeenclosure NW No copyNOFFICE IMAB gIMAB i<Im IMA?3 e WMSK D IMi d DCi NAME IMABurgess A nd3aggefB I-CaBer M.icc iM DC%. lDATE 1,2 I Of /97
- I /97 /2/f1 /97 ho1J /97 '// 7OFFICIAL RECORD COPY
IN 97-.?November\wpr 97 easily removable by unauthorized personnel." To correct this situation, INC has modified thedevice design to secure the lock screws by placing a self-adhesive metal foil over the screws.The foil and adhesive are such that the foil is difficult to remove and cannot be removed andreplaced without showing signs of damage. The foil will serve to inhibit unauthorized personnelfrom accessing the screws, and to provide a means to alert the licensee to possible tampering ofthe lock. INC has indicated that it will contact all owners of potentially affected cameras, onrecord with it, to notify them of the retrofit, and to retrofit the cameras for them or to provide themwith the foil covers and instructions on retrofitting the devices. Attachment 1 contains a copy ofthe retrofit letter.All affected cameras should be retrofitted as soon as possible. Licensees should contact INC, orthe State of California, to obtain retrofit kits or assistance with retrofit procedures, or to report thatthey have not received their kits. Affected cameras may be checked for completed retrofitsduring any inspection.This information notice requires no specific action nor written response. If you have anyquestions about the information in this notice, please contact one of the technical contacts listedbelow or the appropriate regional office.Donald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Material Safetyand SafeguardsTechnical Contacts: David WesleyDept. of Health ServicesState of California(916) 445-1884Michele Burgess, NMSS(301) 415-5868E-mail: mlb5@nrc.govAttachments:1. INC retrofit letter2. List of Recently Issued NRC Information Notices3. List of Recently Issued NMSS Information NoticesDistribution:SSSS rH NE02-SSD-3 KRamsey, IMOBCoordinated with State of California PX-aDOCUMENT NAME: A:iR100N.IN EKraus via fax 10124197To recelve a copy of this document, Indicate I the box: 'C" a Copy w thout attachmentenclosure "E"
- Copy with atachment/endosure AND m No copyl OFFICE IMAB m IMAB I IMAB 'n0- 1 IMORt\ IMPS W 14% LNAME MMBurgesslmb 1SBaggett LCamper IJPiqw 1DC4 //DATE /,2 / Oe /97 7 Y 7 /97 12f 9 1- /97 I-i/ r-\47OFFICIAL RECORD COPY
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake, Uranium Hexafluoride)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
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