|
|
Line 14: |
Line 14: |
| | page count = 9 | | | page count = 9 |
| }} | | }} |
| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDSWASHINGTON, D.C. 20555-0001October 27, 1995NRC INFORMATION NOTICE 95-51: RECENT INCIDENTS INVOLVING POTENTIAL LOSS OFCONTROL OF LICENSED MATERIAL | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS=== |
| | WASHINGTON, D.C. 20555-0001 October 27, 1995 NRC INFORMATION |
| | |
| | NOTICE 95-51: RECENT INCIDENTS |
| | |
| | INVOLVING |
| | |
| | POTENTIAL |
| | |
| | LOSS OF CONTROL OF LICENSED MATERIAL |
|
| |
|
| ==Addressees== | | ==Addressees== |
Line 20: |
Line 33: |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission is issuing this information notice toalert addressees to two recent incidents involving potential loss of controlof licensed material, resulting in internal contamination of individuals. Itis expected that recipients will review the information for applicability totheir facilities and consider actions, as appropriate, to avoid similarproblems. However, suggestions contained in this information notice are notnew NRC requirements; therefore, no specific action nor written response isrequired. | | The U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | is issuing this information |
| | |
| | notice to alert addressees |
| | |
| | to two recent incidents |
| | |
| | involving |
| | |
| | potential |
| | |
| | loss of control of licensed material, resulting |
| | |
| | in internal contamination |
| | |
| | of individuals. |
| | |
| | It is expected that recipients |
| | |
| | will review the information |
| | |
| | for applicability |
| | |
| | to their facilities |
| | |
| | and consider actions, as appropriate, to avoid similar problems. |
| | |
| | However, suggestions |
| | |
| | contained |
| | |
| | in this information |
| | |
| | notice are not new NRC requirements; |
| | therefore, no specific action nor written response is required.Description |
| | |
| | of Circumstances |
| | |
| | Recently, NRC was informed of and responded |
| | |
| | to two incidents |
| | |
| | involving phosphorus-32 (P-32) internal contamination |
| | |
| | of individuals |
| | |
| | at biomedical |
| | |
| | research facilities. |
| | |
| | P-32 is widely used in research institutions, as are many other radionuclides. |
| | |
| | Although these incidents |
| | |
| | both involved P-32, the inherent security issues extend to all facilities |
| | |
| | using licensed material.Case 1: On June 30, 1995, a licensee informed NRC that an incident involving internal contamination |
| | |
| | of a female researcher |
| | |
| | had been reported to the licensee's |
| | |
| | radiation |
| | |
| | safety office the previous evening. The researcher |
| | |
| | was in her fourth month of pregnancy |
| | |
| | at the time of the incident. |
| | |
| | Contamination |
| | |
| | was detected when the researcher's |
| | |
| | husband, who worked with her at the licensee's |
| | |
| | facility, performed |
| | |
| | a routine survey of their lab. The licensee identified |
| | |
| | the radionuclide |
| | |
| | as P-32. Accidental |
| | |
| | contamination |
| | |
| | appeared unlikely because the woman had stopped working with radioactive |
| | |
| | material in their lab about a month before, and because the radioisotope (P-32) identified |
| | |
| | in bioassay samples is not of the same type her lab used. Licensee security officials |
| | |
| | and the Federal Bureau of Investigation |
| | |
| | are investigating |
| | |
| | the possibility |
| | |
| | that the woman ingested food or liquids deliberately |
| | |
| | contaminated |
| | |
| | with the radioisotope. |
| | |
| | Initial calculations (now being refined by NRC, the licensee, and the researcher's |
| | |
| | own technical |
| | |
| | experts) estimated |
| | |
| | that the researcher |
| | |
| | ingested tens of megabecquerels (hundreds |
| | |
| | of microcuries) |
| | of P-32.TVR on q5.osinI q gj0'11 IN 95-51 October 27, 1995 Subsequent |
| | |
| | licensee surveys identified |
| | |
| | a few droplets of P-32 on the floor in front of a refrigerator |
| | |
| | in a lounge adjacent to labs the couple use and an internally |
| | |
| | contaminated |
| | |
| | water cooler in the same building. |
| | |
| | Urine bioassays |
| | |
| | of other workers identified |
| | |
| | approximately |
| | |
| | 25 additional |
| | |
| | individuals |
| | |
| | who have low-level |
| | |
| | internal P-32 contamination. |
| | |
| | In early July 1995, NRC sent an Augmented |
| | |
| | Inspection |
| | |
| | Team to investigate |
| | |
| | the circumstances |
| | |
| | surrounding |
| | |
| | the contamination |
| | |
| | incident. |
| | |
| | While the inspection |
| | |
| | and investigations |
| | |
| | are ongoing, NRC has obtained licensee agreement |
| | |
| | to improve the control of radioactive |
| | |
| | materials |
| | |
| | used in its biological |
| | |
| | and medical research programs.Case 2: On October 16, 1995, a licensee informed NRC that an incident involving |
| | |
| | internal contamination |
| | |
| | of a researcher |
| | |
| | had occurred at its facility almost 2 months earlier. Licensee officials |
| | |
| | told NRC staff that they had not reported the incident earlier because their analyses suggest that the researcher's |
| | |
| | internal dose was below the 10 CFR Part 20 reporting |
| | |
| | criteria.According |
| | |
| | to the licensee, the researcher |
| | |
| | discovered |
| | |
| | that he was contaminated |
| | |
| | during a routine survey of his work area. Also according |
| | |
| | to the licensee, it subsequently |
| | |
| | detected P-32 contamination |
| | |
| | on an item of clothing that the researcher |
| | |
| | had worn earlier that week, when he had last handled P-32 in the laboratory. |
| | |
| | The licensee performed |
| | |
| | urine bioassays, and informed the researcher |
| | |
| | that he may have ingested what was described |
| | |
| | as a drop of P-32 containing |
| | |
| | 21.4 megabecquerel |
| | |
| | (579 microcuries). |
| | |
| | The researcher |
| | |
| | has told licensee campus police that he believes the contamination |
| | |
| | was not accidental. |
| | |
| | NRC and campus police are investigating |
| | |
| | his allegation. |
| | |
| | Also, the researcher |
| | |
| | has requested |
| | |
| | that an independent |
| | |
| | consultant |
| | |
| | prepare a second dose estimate.The licensee initially |
| | |
| | secured all radioactive |
| | |
| | materials |
| | |
| | in the lab after discovery |
| | |
| | of the contamination |
| | |
| | event. Since then, the licensee has permitted |
| | |
| | work with radioactive |
| | |
| | material to resume, after requiring |
| | |
| | more stringent |
| | |
| | inventory |
| | |
| | and accountability |
| | |
| | in the lab and tightening |
| | |
| | security. |
| | |
| | On October 17, 1995, NRC dispatched |
| | |
| | an Incident Investigation |
| | |
| | Team to the licensee's |
| | |
| | site to begin an immediate |
| | |
| | investigation |
| | |
| | of the incident. |
| | |
| | NRC also sent a letter to the licensee requiring |
| | |
| | that certain steps be taken, ensuring among other things that control of radioisotopes |
| | |
| | is adequate to provide reasonable |
| | |
| | assurance |
| | |
| | against another such incident. |
| | |
| | NRC's investigation |
| | |
| | is ongoing. |
| | |
| | IN 95-51 October 27, 1995 Discussion |
| | |
| | The two recent P-32 internal contamination |
| | |
| | incidents |
| | |
| | raise a number of safety and regulatory |
| | |
| | issues. NRC is reviewing |
| | |
| | its regulations |
| | |
| | to determine |
| | |
| | if they need to be revised in light of these events. Among these issues are radioactive |
| | |
| | material security and accountability, survey procedures, preparation |
| | |
| | for bioassays, and reporting |
| | |
| | requirements. |
| | |
| | Each of these issues is addressed |
| | |
| | separately |
| | |
| | below.a. Security. |
| | |
| | In controlled |
| | |
| | or unrestricted |
| | |
| | areas, licensees |
| | |
| | are required by 10 CFR 20.1801 and 20.1802 to secure stored material, and to control and maintain, under constant surveillance, licensed material that is not in storage. Access to restricted |
| | |
| | areas is required to be controlled |
| | |
| | to prevent unauthorized |
| | |
| | access to licensed material. |
| | |
| | Licensees |
| | |
| | should review their programs to ensure that they have a radiation |
| | |
| | safety program in place that will prevent deliberate |
| | |
| | misuse of radioactive |
| | |
| | materials |
| | |
| | in all licensee areas.b. Accountability. |
| | |
| | 10 CFR Part 20 requires the reporting |
| | |
| | of theft or loss of materials |
| | |
| | above defined levels. In addition, the Draft Regulatory |
| | |
| | Guide DG-0005, "Applications |
| | |
| | for Licenses of Broad Scope," published |
| | |
| | for comment in October 1994, states that license applicants: |
| | ... should develop and maintain a strong inventory |
| | |
| | and accountability |
| | |
| | system. The institution |
| | |
| | should have the capability |
| | |
| | to continually |
| | |
| | track incoming shipments |
| | |
| | of licensed material and account for material usage, decay, transfer, and disposal. |
| | |
| | A licensee's |
| | |
| | inventory |
| | |
| | and control system should have the capability |
| | |
| | to ensure that licensed possession |
| | |
| | limits are not exceeded and that material is accounted |
| | |
| | for throughout |
|
| |
|
| ==Description of Circumstances==
| | the institution |
| Recently, NRC was informed of and responded to two incidents involvingphosphorus-32 (P-32) internal contamination of individuals at biomedicalresearch facilities. P-32 is widely used in research institutions, as aremany other radionuclides. Although these incidents both involved P-32, theinherent security issues extend to all facilities using licensed material.Case 1: On June 30, 1995, a licensee informed NRC that an incident involvinginternal contamination of a female researcher had been reported tothe licensee's radiation safety office the previous evening. Theresearcher was in her fourth month of pregnancy at the time of theincident. Contamination was detected when the researcher's husband,who worked with her at the licensee's facility, performed a routinesurvey of their lab. The licensee identified the radionuclide asP-32. Accidental contamination appeared unlikely because the womanhad stopped working with radioactive material in their lab about amonth before, and because the radioisotope (P-32) identified inbioassay samples is not of the same type her lab used. Licenseesecurity officials and the Federal Bureau of Investigation areinvestigating the possibility that the woman ingested food orliquids deliberately contaminated with the radioisotope. Initialcalculations (now being refined by NRC, the licensee, and theresearcher's own technical experts) estimated that the researcheringested tens of megabecquerels (hundreds of microcuries) of P-32.TVR on q5.osinI q gj0'11 IN 95-51October 27, 1995 Subsequent licensee surveys identified a few droplets of P-32 on thefloor in front of a refrigerator in a lounge adjacent to labs thecouple use and an internally contaminated water cooler in the samebuilding. Urine bioassays of other workers identified approximately25 additional individuals who have low-level internal P-32contamination. In early July 1995, NRC sent an Augmented InspectionTeam to investigate the circumstances surrounding the contaminationincident. While the inspection and investigations are ongoing, NRChas obtained licensee agreement to improve the control ofradioactive materials used in its biological and medical researchprograms.Case 2: On October 16, 1995, a licensee informed NRC that an incidentinvolving internal contamination of a researcher had occurred at itsfacility almost 2 months earlier. Licensee officials told NRC staffthat they had not reported the incident earlier because theiranalyses suggest that the researcher's internal dose was below the10 CFR Part 20 reporting criteria.According to the licensee, the researcher discovered that he wascontaminated during a routine survey of his work area. Alsoaccording to the licensee, it subsequently detected P-32contamination on an item of clothing that the researcher had wornearlier that week, when he had last handled P-32 in the laboratory.The licensee performed urine bioassays, and informed the researcherthat he may have ingested what was described as a drop of P-32containing 21.4 megabecquerel (579 microcuries). The researcher hastold licensee campus police that he believes the contamination wasnot accidental. NRC and campus police are investigating hisallegation. Also, the researcher has requested that an independentconsultant prepare a second dose estimate.The licensee initially secured all radioactive materials in the labafter discovery of the contamination event. Since then, thelicensee has permitted work with radioactive material to resume,after requiring more stringent inventory and accountability in thelab and tightening security. On October 17, 1995, NRC dispatched anIncident Investigation Team to the licensee's site to begin animmediate investigation of the incident. NRC also sent a letter tothe licensee requiring that certain steps be taken, ensuring amongother things that control of radioisotopes is adequate to providereasonable assurance against another such incident. NRC'sinvestigation is ongoing.
| |
|
| |
|
| IN 95-51October 27, 1995 DiscussionThe two recent P-32 internal contamination incidents raise a number of safetyand regulatory issues. NRC is reviewing its regulations to determine if theyneed to be revised in light of these events. Among these issues areradioactive material security and accountability, survey procedures,preparation for bioassays, and reporting requirements. Each of these issuesis addressed separately below.a. Security. In controlled or unrestricted areas, licensees arerequired by 10 CFR 20.1801 and 20.1802 to secure stored material,and to control and maintain, under constant surveillance, licensedmaterial that is not in storage. Access to restricted areas isrequired to be controlled to prevent unauthorized access to licensedmaterial. Licensees should review their programs to ensure thatthey have a radiation safety program in place that will preventdeliberate misuse of radioactive materials in all licensee areas.b. Accountability. 10 CFR Part 20 requires the reporting of theft orloss of materials above defined levels. In addition, the DraftRegulatory Guide DG-0005, "Applications for Licenses of BroadScope," published for comment in October 1994, states that licenseapplicants:... should develop and maintain a strong inventory andaccountability system. The institution should have thecapability to continually track incoming shipments oflicensed material and account for material usage, decay,transfer, and disposal. A licensee's inventory and controlsystem should have the capability to ensure that licensedpossession limits are not exceeded and that material isaccounted for throughout the institution at any given time.In light of these events, licensees should review their programs todetermine whether they need to improve their radioactive materialaccountability systems, commensurate with the scope of theirprograms.c. Detecting licensed material. NRC emphasizes that conducting surveyswith adequate, calibrated equipment is a crucial step in conductingsafe operations. Many commercially available survey instruments,such as Geiger-Mueller detectors, are capable of detecting P-32,even after ingestion, in the activity range used in researchfacilities. In both of these cases, internal contamination wasoriginally detected when the researchers conducted routine surveysof their laboratories and detected high background readings.Licensees should review their programs to ensure that they areconducting surveys with adequate, calibrated equipment.
| | at any given time.In light of these events, licensees |
|
| |
|
| IN 95-51October 27, 1995 d. Bioassay preparation. All licensees are responsible for respondingto incidents. Some licensees already have bioassay programs inplace to comply with the requirement in 10 CFR 20.1502 to monitorworkers whose intake is likely to exceed 10 percent of theoccupational dose limits. Interpretation of bioassay data, whenregulatory thresholds are approached, may be difficult. Importantinformation on the proper conduct of a bioassay program is providedin Regulatory Guide 8.9, Rev. 1, July 1993, "Acceptable Concepts,Models, Equations, and Assumptions for a Btoassay Program" andNUREG/CR-4884, 'Interpretation of Bioassay Measurements." Licenseesthat need immediate medical consultation to respond to an ongoinginternal contamination event can contact the Radiation EmergencyAssistance Center/Training Site (REAC/TS), which is funded by theU.S. Department of Energy to provide consultation in suchsituations. The NRC Operations Center can connect callers withREAC/TS.If internal contamination is detected, health physics consultantsare commercially available to assist with bioassay and otherresponse measures. However, licensees that plan to use consultantsmay want to identify and make arrangements for those resources now,rather than wait until an incident occurs. Licensees that need helpin identifying health physics services should contact professionalsocieties or organizations for references.e. Food and beverage storage. Generally, licensees have proceduresprohibiting eating, drinking, and smoking in radiologicallyrestricted areas. In light of these events, licensees should reviewtheir programs to determine how food, particularly lunches, snackfoods, and beverages in unsealed containers, are permitted or storedin their facilities.f. Contact NRC if deliberate misuse of licensed material is suspected.NRC considers deliberate misuse of licensed material to be ofsignificant regulatory interest, and expects to be contacted in suchsituations. Although the magnitude of the dose could be withinNRC's regulatory limits, the possibility that such a dose wasdelivered intentionally, and possibly with malice, raises concernsabout a licensee's, a contractor's, or any employee's deliberatemisconduct, as addressed in 10 CFR 30.10, 40.10, 70.10, and 72.12.In addition, pursuant to 10 CFR 30.9(b), 40.9(b), 70.9(b), and72.11(b), each licensee is required to I... notify the Commission ofinformation identified ... as having for the regulated activity asignificant implication for public health and safety ...."Notification shall be provided in such cases to the RegionalAdministrator within 2 working days.
| | should review their programs to determine |
|
| |
|
| IN 95-51October 27, 995The issues raised in these two cases should leadreexamining their own methods to prevent and, ifinternal contamination incidents.licensees to considernecessary, respond toThe Information in this noticeinspections in these two casesas necessary, once results areis preliminary, and the investigations andare ongoing. NRC may issue further guidance,known and conclusions drawn on these two cases.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contacts listed below or the appropriate regional office."fA' 4~dlDonald A. Cool, DirectorDivision of Industrial andMedical Nuclear SafetyOffice of Nuclear Materialand SafeguardsSafetyTechnical contacts:Scott Moore, NMSS(301) 415-7875B. J.(708)Holt, RIII829-9836Mohamed Shanbaky, RI(610) 337-5209John Potter, RII(404) 331-5571Thomas Kozak, RIII(708) 829-9866Linda Howell, RIV(817) 860-8213Attachments:1. List of Emergency Contacts2. List of Recently Issued NMSS Information Notices3. List of Recently Issued NRC Information Notices~ 6 t i :'-TX a
| | whether they need to improve their radioactive |
|
| |
|
| Atta Pnt 1IN 9'-s-1October 27, 1995 LIST OF EMERGENCY | | material accountability |
| | |
| | systems, commensurate |
| | |
| | with the scope of their programs.c. Detecting |
| | |
| | licensed material. |
| | |
| | NRC emphasizes |
| | |
| | that conducting |
| | |
| | surveys with adequate, calibrated |
| | |
| | equipment |
| | |
| | is a crucial step in conducting |
| | |
| | safe operations. |
| | |
| | Many commercially |
| | |
| | available |
| | |
| | survey instruments, such as Geiger-Mueller |
| | |
| | detectors, are capable of detecting |
| | |
| | P-32, even after ingestion, in the activity range used in research facilities. |
| | |
| | In both of these cases, internal contamination |
| | |
| | was originally |
| | |
| | detected when the researchers |
| | |
| | conducted |
| | |
| | routine surveys of their laboratories |
| | |
| | and detected high background |
| | |
| | readings.Licensees |
| | |
| | should review their programs to ensure that they are conducting |
| | |
| | surveys with adequate, calibrated |
| | |
| | equipment. |
| | |
| | IN 95-51 October 27, 1995 d. Bioassay preparation. |
| | |
| | All licensees |
| | |
| | are responsible |
| | |
| | for responding |
| | |
| | to incidents. |
| | |
| | Some licensees |
| | |
| | already have bioassay programs in place to comply with the requirement |
| | |
| | in 10 CFR 20.1502 to monitor workers whose intake is likely to exceed 10 percent of the occupational |
| | |
| | dose limits. Interpretation |
| | |
| | of bioassay data, when regulatory |
| | |
| | thresholds |
| | |
| | are approached, may be difficult. |
| | |
| | Important information |
| | |
| | on the proper conduct of a bioassay program is provided in Regulatory |
| | |
| | Guide 8.9, Rev. 1, July 1993, "Acceptable |
| | |
| | Concepts, Models, Equations, and Assumptions |
| | |
| | for a Btoassay Program" and NUREG/CR-4884, 'Interpretation |
| | |
| | of Bioassay Measurements." Licensees that need immediate |
| | |
| | medical consultation |
| | |
| | to respond to an ongoing internal contamination |
| | |
| | event can contact the Radiation |
| | |
| | Emergency Assistance |
| | |
| | Center/Training |
| | |
| | Site (REAC/TS), which is funded by the U.S. Department |
| | |
| | of Energy to provide consultation |
| | |
| | in such situations. |
| | |
| | The NRC Operations |
| | |
| | Center can connect callers with REAC/TS.If internal contamination |
| | |
| | is detected, health physics consultants |
| | |
| | are commercially |
| | |
| | available |
| | |
| | to assist with bioassay and other response measures. |
| | |
| | However, licensees |
| | |
| | that plan to use consultants |
| | |
| | may want to identify and make arrangements |
| | |
| | for those resources |
| | |
| | now, rather than wait until an incident occurs. Licensees |
| | |
| | that need help in identifying |
| | |
| | health physics services should contact professional |
| | |
| | societies |
| | |
| | or organizations |
| | |
| | for references. |
| | |
| | e. Food and beverage storage. Generally, licensees |
| | |
| | have procedures |
| | |
| | prohibiting |
| | |
| | eating, drinking, and smoking in radiologically |
| | |
| | restricted |
| | |
| | areas. In light of these events, licensees |
| | |
| | should review their programs to determine |
| | |
| | how food, particularly |
| | |
| | lunches, snack foods, and beverages |
| | |
| | in unsealed containers, are permitted |
| | |
| | or stored in their facilities. |
| | |
| | f. Contact NRC if deliberate |
| | |
| | misuse of licensed material is suspected. |
| | |
| | NRC considers |
| | |
| | deliberate |
| | |
| | misuse of licensed material to be of significant |
| | |
| | regulatory |
| | |
| | interest, and expects to be contacted |
| | |
| | in such situations. |
| | |
| | Although the magnitude |
| | |
| | of the dose could be within NRC's regulatory |
| | |
| | limits, the possibility |
| | |
| | that such a dose was delivered |
| | |
| | intentionally, and possibly with malice, raises concerns about a licensee's, a contractor's, or any employee's |
| | |
| | deliberate |
| | |
| | misconduct, as addressed |
| | |
| | in 10 CFR 30.10, 40.10, 70.10, and 72.12.In addition, pursuant to 10 CFR 30.9(b), 40.9(b), 70.9(b), and 72.11(b), each licensee is required to I... notify the Commission |
| | |
| | of information |
| | |
| | identified |
| | |
| | ... as having for the regulated |
| | |
| | activity a significant |
| | |
| | implication |
| | |
| | for public health and safety ...." Notification |
| | |
| | shall be provided in such cases to the Regional Administrator |
| | |
| | within 2 working days. |
| | |
| | IN 95-51 October 27, 1995 The issues raised in these two cases should lead reexamining |
| | |
| | their own methods to prevent and, if internal contamination |
| | |
| | incidents. |
| | |
| | licensees |
| | |
| | to consider necessary, respond to The Information |
| | |
| | in this notice inspections |
| | |
| | in these two cases as necessary, once results are is preliminary, and the investigations |
| | |
| | and are ongoing. NRC may issue further guidance, known and conclusions |
| | |
| | drawn on these two cases.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | regional office."fA' 4~dl Donald A. Cool, Director Division of Industrial |
| | |
| | and Medical Nuclear Safety Office of Nuclear Material and Safeguards |
| | |
| | Safety Technical |
| | |
| | contacts: Scott Moore, NMSS (301) 415-7875 B. J.(708)Holt, RIII 829-9836 Mohamed Shanbaky, RI (610) 337-5209 John Potter, RII (404) 331-5571 Thomas Kozak, RIII (708) 829-9866 Linda Howell, RIV (817) 860-8213 Attachments: |
| | 1. List of Emergency |
| | |
| | Contacts 2. List of Recently Issued NMSS Information |
| | |
| | Notices 3. List of Recently Issued NRC Information |
| | |
| | Notices~ 6 t i :'-TX a |
| | |
| | Atta Pnt 1 IN 9'-s-1 October 27, 1995 LIST OF EMERGENCY |
|
| |
|
| ==CONTACT== | | ==CONTACT== |
| SI. NRC Operations CenterTelephone: 301-816-5100II. Radiation Emergency Assi!Daytime Telephone: 423-!24-hour Telephone: 423-4(to consult with a physli(will accept collect calls)stance Center/Training Site (REAC/TS)576-3131481-1000 (ask for REAC/TS):ian)
| | S I. NRC Operations |
| Attachment 2IN 95-51October 27, 1995 LIST OF RECENTLY ISSUEDNMSS INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-5095-4495-3995-2995-2895-2594-64,Supp. 195-07Safety Defect in Gammamed12i Bronchial CatheterClamping AdaptersEnsuring Compatible Use ofDrive Cables IncorporatingIndustrial Nuclear CompanyBall-type Male ConnectorsBrachytherapy IncidentsInvcyving TreatmentPlanning ErrorsOversight of Design andand Fabrication Activitiesfor Metal Components Usedin Spent Fuel Dry StorageSystemsEmplacement of SupportPads for Spent Fuel DryStorage Installations atReactor SitesValve Failure duringPatient Treatment withGamma StereotacticRadiosurgery UnitReactivity Insertion Trans-ient and Accident Limitsfor High Burnup FuelRadiopharmaceutical VialBreakage during Preparation10/30/9509/26/9509/19/9506/07/9506/05/9505/11/9504/06/9501/27/95All High Dose RateAfterloader (HDR) Licensees.All Radiography Licensees.All U.S. Nuclear RegulatoryCommission MedicalLicensees.All holders of OLs or CPsfor nuclear power reactors.Independent spent fuelstorage installationdesigners and fabricators.All holders of OLs or CPsfor nuclear power reactorsAll U.S. Nuclear RegulatoryCommission MedicalLicensees.All holders of OLs or CPsfor Nuclear Power Reactorsand all fuel fabricationlicensees.All U.S. Nuclear RegulatoryCommission medical licenseesauthorized to use byproductmaterial for diagnosticprocedures. | | |
| | Center Telephone: |
| | 301-816-5100 |
| | II. Radiation |
| | |
| | Emergency |
| | |
| | Assi!Daytime Telephone: |
| | 423-!24-hour Telephone: |
| | 423-4 (to consult with a physli (will accept collect calls)stance Center/Training |
| | |
| | Site (REAC/TS)576-3131 481-1000 (ask for REAC/TS):ian) |
| | Attachment |
| | |
| | 2 IN 95-51 October 27, 1995 LIST OF RECENTLY ISSUED NMSS INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 95-50 95-44 95-39 95-29 95-28 95-25 94-64, Supp. 1 95-07 Safety Defect in Gammamed 12i Bronchial |
| | |
| | Catheter Clamping Adapters Ensuring Compatible |
| | |
| | ===Use of Drive Cables Incorporating=== |
| | Industrial |
| | |
| | Nuclear Company Ball-type |
| | |
| | ===Male Connectors=== |
| | Brachytherapy |
| | |
| | Incidents Invcyving |
| | |
| | Treatment Planning Errors Oversight |
| | |
| | of Design and and Fabrication |
| | |
| | Activities |
| | |
| | for Metal Components |
| | |
| | Used in Spent Fuel Dry Storage Systems Emplacement |
| | |
| | of Support Pads for Spent Fuel Dry Storage Installations |
| | |
| | at Reactor Sites Valve Failure during Patient Treatment |
| | |
| | with Gamma Stereotactic |
| | |
| | Radiosurgery |
| | |
| | Unit Reactivity |
| | |
| | Insertion |
| | |
| | Trans-ient and Accident Limits for High Burnup Fuel Radiopharmaceutical |
| | |
| | ===Vial Breakage during Preparation=== |
| | 10/30/95 09/26/95 09/19/95 06/07/95 06/05/95 05/11/95 04/06/95 01/27/95 All High Dose Rate Afterloader (HDR) Licensees. |
| | |
| | All Radiography |
| | |
| | Licensees. |
| | |
| | ===All U.S. Nuclear Regulatory=== |
| | Commission |
| | |
| | Medical Licensees. |
| | |
| | All holders of OLs or CPs for nuclear power reactors.Independent |
| | |
| | spent fuel storage installation |
| | |
| | designers |
| | |
| | and fabricators. |
| | |
| | All holders of OLs or CPs for nuclear power reactors All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | Medical Licensees. |
| | |
| | All holders of OLs or CPs for Nuclear Power Reactors and all fuel fabrication |
| | |
| | licensees. |
| | |
| | ===All U.S. Nuclear Regulatory=== |
| | Commission |
| | |
| | medical licensees authorized |
| | |
| | to use byproduct material for diagnostic |
| | |
| | procedures. |
| | |
| | Attachment |
| | |
| | 3 IN 95-51 October 27, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 95-50 95-49 95-48 95-47 95-46 Safety Defect in Gammamed 121 Bronchial |
| | |
| | Catheter Clamping Adapters Seismic Adequacy of Thermo-Lag |
| | |
| | Panels Results of Shift Staffing Study Unexpected |
| | |
| | Opening of a Safety/Relief |
| | |
| | Valve and Complications |
| | |
| | Involving Suppression |
| | |
| | ===Pool Cooling Strainer Blockage Unplanned, Undetected=== |
| | Release of Radioactivity |
| | |
| | from the Exhaust Ventilation |
| | |
| | System of a Boiling Water Reactor Potentially |
| | |
| | ===Nonconforming=== |
| | Fasteners |
| | |
| | Supplied by A&G Engineering |
| | |
| | II, Inc.American Power Service Falsification |
| | |
| | of American Society for Nondestructive |
| | |
| | Testing (ASNT) Certificates |
| | |
| | Ensuring Compatible |
| | |
| | ===Use of Drive Cables Incorporating=== |
| | Industrial |
| | |
| | Nuclear Company Ball-Type |
| | |
| | ===Male Connectors=== |
| | Failure of the Bolt-Locking |
| | |
| | Device on the Reactor Coolant Pump Turning Vane 10/30/95 10/27/95 10/10/95 10/04/95 10/06/95 10/05/95 10/04/95 09/26/95 09/28/95 All High Dose Rate Afterloader (HDR) Adapters.All holders of OLs or CPs for nuclear power reactors.All holders of OL,. or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All Radiography |
| | |
| | Licensees. |
| | |
| | All holders of OLs or CPs for nuclear power reactors designed by Westinghouse |
| | |
| | Electric Corporation (W).95-12, Supp. 1 95-45 95-44 95-43 OL -Operating |
| | |
| | License CP -Construction |
| | |
| | Permit |
| | |
| | 0 1, .-:-V/I DOCUMENT NAME: G:INCIDENT.SWM |
|
| |
|
| Attachment 3IN 95-51October 27, 1995 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-5095-4995-4895-4795-46Safety Defect in Gammamed121 Bronchial CatheterClamping AdaptersSeismic Adequacy ofThermo-Lag PanelsResults of Shift StaffingStudyUnexpected Opening of aSafety/Relief Valve andComplications InvolvingSuppression Pool CoolingStrainer BlockageUnplanned, UndetectedRelease of Radioactivityfrom the Exhaust VentilationSystem of a Boiling WaterReactorPotentially NonconformingFasteners Supplied byA&G Engineering II, Inc.American Power ServiceFalsification of AmericanSociety for NondestructiveTesting (ASNT) CertificatesEnsuring Compatible Use ofDrive Cables IncorporatingIndustrial Nuclear CompanyBall-Type Male ConnectorsFailure of the Bolt-LockingDevice on the ReactorCoolant Pump Turning Vane10/30/9510/27/9510/10/9510/04/9510/06/9510/05/9510/04/9509/26/9509/28/95All High Dose RateAfterloader (HDR) Adapters.All holders of OLs or CPsfor nuclear power reactors.All holders of OL,. or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All Radiography Licensees.All holders of OLs or CPsfor nuclear power reactorsdesigned by WestinghouseElectric Corporation (W).95-12,Supp. 195-4595-4495-43OL -Operating LicenseCP -Construction Permit
| | To receive a copy of this document, indicate in the box: *C. Copy without attachment/enct. |
|
| |
|
| 0 1, .-:-V/IDOCUMENT NAME: G:INCIDENT.SWMTo receive a copy of this document, indicate in the box: *C. Copy without attachment/enct. E = Copy with attachmentlenclNz N Lo copy -0 i 1KANE j Moore "JQones l 6 Pn rn / Caputo STreby XDATE /0OFC TechEd l ASVAli*l> INNX l. lKANE F _ __EK___ __GusDATE Io/aV/4( 1 _lOFFICIAL RECORD COPY
| | E = Copy with attachmentlencl |
|
| |
|
| }} | | Nz N Lo copy -0 i 1 KANE j Moore "JQones l 6 Pn rn / Caputo STreby X DATE /0 OFC TechEd l ASVAli*l> |
| | INNX l. l KANE F _ __EK___ __Gus DATE Io/aV/4( 1 _l OFFICIAL RECORD COPY}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Recent Incidents Involving Potential Loss of Control of Licensed MaterialML031060161 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Issue date: |
10/27/1995 |
---|
From: |
Cool D A NRC/NMSS/IMNS |
---|
To: |
|
---|
References |
---|
IN-95-051, NUDOCS 9510260330 |
Download: ML031060161 (9) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555-0001 October 27, 1995 NRC INFORMATION
NOTICE 95-51: RECENT INCIDENTS
INVOLVING
POTENTIAL
LOSS OF CONTROL OF LICENSED MATERIAL
Addressees
All material and fuel cycle licensees.
Purpose
The U.S. Nuclear Regulatory
Commission
is issuing this information
notice to alert addressees
to two recent incidents
involving
potential
loss of control of licensed material, resulting
in internal contamination
of individuals.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not new NRC requirements;
therefore, no specific action nor written response is required.Description
of Circumstances
Recently, NRC was informed of and responded
to two incidents
involving phosphorus-32 (P-32) internal contamination
of individuals
at biomedical
research facilities.
P-32 is widely used in research institutions, as are many other radionuclides.
Although these incidents
both involved P-32, the inherent security issues extend to all facilities
using licensed material.Case 1: On June 30, 1995, a licensee informed NRC that an incident involving internal contamination
of a female researcher
had been reported to the licensee's
radiation
safety office the previous evening. The researcher
was in her fourth month of pregnancy
at the time of the incident.
Contamination
was detected when the researcher's
husband, who worked with her at the licensee's
facility, performed
a routine survey of their lab. The licensee identified
the radionuclide
as P-32. Accidental
contamination
appeared unlikely because the woman had stopped working with radioactive
material in their lab about a month before, and because the radioisotope (P-32) identified
in bioassay samples is not of the same type her lab used. Licensee security officials
and the Federal Bureau of Investigation
are investigating
the possibility
that the woman ingested food or liquids deliberately
contaminated
with the radioisotope.
Initial calculations (now being refined by NRC, the licensee, and the researcher's
own technical
experts) estimated
that the researcher
ingested tens of megabecquerels (hundreds
of microcuries)
of P-32.TVR on q5.osinI q gj0'11 IN 95-51 October 27, 1995 Subsequent
licensee surveys identified
a few droplets of P-32 on the floor in front of a refrigerator
in a lounge adjacent to labs the couple use and an internally
contaminated
water cooler in the same building.
Urine bioassays
of other workers identified
approximately
25 additional
individuals
who have low-level
internal P-32 contamination.
In early July 1995, NRC sent an Augmented
Inspection
Team to investigate
the circumstances
surrounding
the contamination
incident.
While the inspection
and investigations
are ongoing, NRC has obtained licensee agreement
to improve the control of radioactive
materials
used in its biological
and medical research programs.Case 2: On October 16, 1995, a licensee informed NRC that an incident involving
internal contamination
of a researcher
had occurred at its facility almost 2 months earlier. Licensee officials
told NRC staff that they had not reported the incident earlier because their analyses suggest that the researcher's
internal dose was below the 10 CFR Part 20 reporting
criteria.According
to the licensee, the researcher
discovered
that he was contaminated
during a routine survey of his work area. Also according
to the licensee, it subsequently
detected P-32 contamination
on an item of clothing that the researcher
had worn earlier that week, when he had last handled P-32 in the laboratory.
The licensee performed
urine bioassays, and informed the researcher
that he may have ingested what was described
as a drop of P-32 containing
21.4 megabecquerel
(579 microcuries).
The researcher
has told licensee campus police that he believes the contamination
was not accidental.
NRC and campus police are investigating
his allegation.
Also, the researcher
has requested
that an independent
consultant
prepare a second dose estimate.The licensee initially
secured all radioactive
materials
in the lab after discovery
of the contamination
event. Since then, the licensee has permitted
work with radioactive
material to resume, after requiring
more stringent
inventory
and accountability
in the lab and tightening
security.
On October 17, 1995, NRC dispatched
an Incident Investigation
Team to the licensee's
site to begin an immediate
investigation
of the incident.
NRC also sent a letter to the licensee requiring
that certain steps be taken, ensuring among other things that control of radioisotopes
is adequate to provide reasonable
assurance
against another such incident.
NRC's investigation
is ongoing.
IN 95-51 October 27, 1995 Discussion
The two recent P-32 internal contamination
incidents
raise a number of safety and regulatory
issues. NRC is reviewing
its regulations
to determine
if they need to be revised in light of these events. Among these issues are radioactive
material security and accountability, survey procedures, preparation
for bioassays, and reporting
requirements.
Each of these issues is addressed
separately
below.a. Security.
In controlled
or unrestricted
areas, licensees
are required by 10 CFR 20.1801 and 20.1802 to secure stored material, and to control and maintain, under constant surveillance, licensed material that is not in storage. Access to restricted
areas is required to be controlled
to prevent unauthorized
access to licensed material.
Licensees
should review their programs to ensure that they have a radiation
safety program in place that will prevent deliberate
misuse of radioactive
materials
in all licensee areas.b. Accountability.
10 CFR Part 20 requires the reporting
of theft or loss of materials
above defined levels. In addition, the Draft Regulatory
Guide DG-0005, "Applications
for Licenses of Broad Scope," published
for comment in October 1994, states that license applicants:
... should develop and maintain a strong inventory
and accountability
system. The institution
should have the capability
to continually
track incoming shipments
of licensed material and account for material usage, decay, transfer, and disposal.
A licensee's
inventory
and control system should have the capability
to ensure that licensed possession
limits are not exceeded and that material is accounted
for throughout
the institution
at any given time.In light of these events, licensees
should review their programs to determine
whether they need to improve their radioactive
material accountability
systems, commensurate
with the scope of their programs.c. Detecting
licensed material.
NRC emphasizes
that conducting
surveys with adequate, calibrated
equipment
is a crucial step in conducting
safe operations.
Many commercially
available
survey instruments, such as Geiger-Mueller
detectors, are capable of detecting
P-32, even after ingestion, in the activity range used in research facilities.
In both of these cases, internal contamination
was originally
detected when the researchers
conducted
routine surveys of their laboratories
and detected high background
readings.Licensees
should review their programs to ensure that they are conducting
surveys with adequate, calibrated
equipment.
IN 95-51 October 27, 1995 d. Bioassay preparation.
All licensees
are responsible
for responding
to incidents.
Some licensees
already have bioassay programs in place to comply with the requirement
in 10 CFR 20.1502 to monitor workers whose intake is likely to exceed 10 percent of the occupational
dose limits. Interpretation
of bioassay data, when regulatory
thresholds
are approached, may be difficult.
Important information
on the proper conduct of a bioassay program is provided in Regulatory
Guide 8.9, Rev. 1, July 1993, "Acceptable
Concepts, Models, Equations, and Assumptions
for a Btoassay Program" and NUREG/CR-4884, 'Interpretation
of Bioassay Measurements." Licensees that need immediate
medical consultation
to respond to an ongoing internal contamination
event can contact the Radiation
Emergency Assistance
Center/Training
Site (REAC/TS), which is funded by the U.S. Department
of Energy to provide consultation
in such situations.
The NRC Operations
Center can connect callers with REAC/TS.If internal contamination
is detected, health physics consultants
are commercially
available
to assist with bioassay and other response measures.
However, licensees
that plan to use consultants
may want to identify and make arrangements
for those resources
now, rather than wait until an incident occurs. Licensees
that need help in identifying
health physics services should contact professional
societies
or organizations
for references.
e. Food and beverage storage. Generally, licensees
have procedures
prohibiting
eating, drinking, and smoking in radiologically
restricted
areas. In light of these events, licensees
should review their programs to determine
how food, particularly
lunches, snack foods, and beverages
in unsealed containers, are permitted
or stored in their facilities.
f. Contact NRC if deliberate
misuse of licensed material is suspected.
NRC considers
deliberate
misuse of licensed material to be of significant
regulatory
interest, and expects to be contacted
in such situations.
Although the magnitude
of the dose could be within NRC's regulatory
limits, the possibility
that such a dose was delivered
intentionally, and possibly with malice, raises concerns about a licensee's, a contractor's, or any employee's
deliberate
misconduct, as addressed
in 10 CFR 30.10, 40.10, 70.10, and 72.12.In addition, pursuant to 10 CFR 30.9(b), 40.9(b), 70.9(b), and 72.11(b), each licensee is required to I... notify the Commission
of information
identified
... as having for the regulated
activity a significant
implication
for public health and safety ...." Notification
shall be provided in such cases to the Regional Administrator
within 2 working days.
IN 95-51 October 27, 1995 The issues raised in these two cases should lead reexamining
their own methods to prevent and, if internal contamination
incidents.
licensees
to consider necessary, respond to The Information
in this notice inspections
in these two cases as necessary, once results are is preliminary, and the investigations
and are ongoing. NRC may issue further guidance, known and conclusions
drawn on these two cases.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contacts listed below or the appropriate
regional office."fA' 4~dl Donald A. Cool, Director Division of Industrial
and Medical Nuclear Safety Office of Nuclear Material and Safeguards
Safety Technical
contacts: Scott Moore, NMSS (301) 415-7875 B. J.(708)Holt, RIII 829-9836 Mohamed Shanbaky, RI (610) 337-5209 John Potter, RII (404) 331-5571 Thomas Kozak, RIII (708) 829-9866 Linda Howell, RIV (817) 860-8213 Attachments:
1. List of Emergency
Contacts 2. List of Recently Issued NMSS Information
Notices 3. List of Recently Issued NRC Information
Notices~ 6 t i :'-TX a
Atta Pnt 1 IN 9'-s-1 October 27, 1995 LIST OF EMERGENCY
CONTACT
S I. NRC Operations
Center Telephone:
301-816-5100
II. Radiation
Emergency
Assi!Daytime Telephone:
423-!24-hour Telephone:
423-4 (to consult with a physli (will accept collect calls)stance Center/Training
Site (REAC/TS)576-3131 481-1000 (ask for REAC/TS):ian)
Attachment
2 IN 95-51 October 27, 1995 LIST OF RECENTLY ISSUED NMSS INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-50 95-44 95-39 95-29 95-28 95-25 94-64, Supp. 1 95-07 Safety Defect in Gammamed 12i Bronchial
Catheter Clamping Adapters Ensuring Compatible
Use of Drive Cables Incorporating
Industrial
Nuclear Company Ball-type
Male Connectors
Brachytherapy
Incidents Invcyving
Treatment Planning Errors Oversight
of Design and and Fabrication
Activities
for Metal Components
Used in Spent Fuel Dry Storage Systems Emplacement
of Support Pads for Spent Fuel Dry Storage Installations
at Reactor Sites Valve Failure during Patient Treatment
with Gamma Stereotactic
Radiosurgery
Unit Reactivity
Insertion
Trans-ient and Accident Limits for High Burnup Fuel Radiopharmaceutical
Vial Breakage during Preparation
10/30/95 09/26/95 09/19/95 06/07/95 06/05/95 05/11/95 04/06/95 01/27/95 All High Dose Rate Afterloader (HDR) Licensees.
All Radiography
Licensees.
All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All holders of OLs or CPs for nuclear power reactors.Independent
spent fuel storage installation
designers
and fabricators.
All holders of OLs or CPs for nuclear power reactors All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All holders of OLs or CPs for Nuclear Power Reactors and all fuel fabrication
licensees.
All U.S. Nuclear Regulatory
Commission
medical licensees authorized
to use byproduct material for diagnostic
procedures.
Attachment
3 IN 95-51 October 27, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-50 95-49 95-48 95-47 95-46 Safety Defect in Gammamed 121 Bronchial
Catheter Clamping Adapters Seismic Adequacy of Thermo-Lag
Panels Results of Shift Staffing Study Unexpected
Opening of a Safety/Relief
Valve and Complications
Involving Suppression
Pool Cooling Strainer Blockage Unplanned, Undetected
Release of Radioactivity
from the Exhaust Ventilation
System of a Boiling Water Reactor Potentially
Nonconforming
Fasteners
Supplied by A&G Engineering
II, Inc.American Power Service Falsification
of American Society for Nondestructive
Testing (ASNT) Certificates
Ensuring Compatible
Use of Drive Cables Incorporating
Industrial
Nuclear Company Ball-Type
Male Connectors
Failure of the Bolt-Locking
Device on the Reactor Coolant Pump Turning Vane 10/30/95 10/27/95 10/10/95 10/04/95 10/06/95 10/05/95 10/04/95 09/26/95 09/28/95 All High Dose Rate Afterloader (HDR) Adapters.All holders of OLs or CPs for nuclear power reactors.All holders of OL,. or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All Radiography
Licensees.
All holders of OLs or CPs for nuclear power reactors designed by Westinghouse
Electric Corporation (W).95-12, Supp. 1 95-45 95-44 95-43 OL -Operating
License CP -Construction
Permit
0 1, .-:-V/I DOCUMENT NAME: G:INCIDENT.SWM
To receive a copy of this document, indicate in the box: *C. Copy without attachment/enct.
E = Copy with attachmentlencl
Nz N Lo copy -0 i 1 KANE j Moore "JQones l 6 Pn rn / Caputo STreby X DATE /0 OFC TechEd l ASVAli*l>
INNX l. l KANE F _ __EK___ __Gus DATE Io/aV/4( 1 _l OFFICIAL RECORD COPY
|
---|
|
list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak, Water hammer)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995, Topic: Operability Determination)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995, Topic: High Energy Line Break)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995, Topic: Feedwater Heater)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown, Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995, Topic: Hardened grease)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995, Topic: Overdose)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Safe Shutdown Earthquake, Tornado Generated Missile, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves, Overspeed trip)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995, Topic: Overspeed)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier, Overspeed trip)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995, Topic: Overspeed trip)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995, Topic: Overspeed)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995, Topic: Overspeed)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Operator Manual Action, Emergency Lighting, Exemption Request, Overspeed)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy, Underdose)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Commercial Grade, Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
... further results |
---|