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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:UNITED STATES |
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|
| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| |
|
| ===OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS===
| | OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS |
| WASHINGTON, D.C. 20555 June 11, 1996 NRC INFORMATION
| |
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| |
|
| NOTICE 96-35: FAILURE OF SAFETY SYSTEMS ON SELF-SHIELDED | | WASHINGTON, D.C. 20555 June 11, 1996 NRC INFORMATION NOTICE 96-35: FAILURE OF SAFETY SYSTEMS ON SELF-SHIELDED |
|
| |
|
| IRRADIATORS | | IRRADIATORS BECAUSE OF INADEQUATE MAINTENANCE |
| | |
| BECAUSE OF INADEQUATE | |
| | |
| MAINTENANCE | |
|
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|
| AND TRAINING | | AND TRAINING |
|
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|
| ==Addressees== | | ==Addressees== |
| All U.S. Nuclear Regulatory | | All U.S. Nuclear Regulatory Commission irradiator licensees and vendors. |
| | |
| Commission | |
| | |
| irradiator | |
| | |
| licensees | |
| | |
| and vendors. | |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information |
| | |
| Commission (NRC) is issuing this information | |
| | |
| notice (IN) to alert addressees
| |
| | |
| to two incidents
| |
| | |
| where safety interlocks
| |
| | |
| on self-shielded
| |
| | |
| irradiators (Category
| |
| | |
| I) failed to prevent inadvertent
| |
| | |
| exposure.The causes of these exposures
| |
| | |
| stemmed from a lack of appropriate
| |
| | |
| maintenance
| |
| | |
| and/or worker training.
| |
| | |
| The incidents
| |
| | |
| include a broken spring -- possibly causing malfunction
| |
| | |
| of the safety interlock
| |
| | |
| -- and a worker who intentionally
| |
| | |
| bypassed a safety interlock.
| |
| | |
| 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 NRC requirements;
| |
| therefore, no specific action nor written response is required.Description
| |
| | |
| of Circumstances
| |
| | |
| The first incident occurred when an operator may have been able to open the shielded door of an irradiator
| |
| | |
| with the sources in the exposed position.After irradiation
| |
| | |
| of several pocket dosimeters, the operator opened the shielded door of the irradiator
| |
| | |
| to retrieve the dosimeters, but did not perform a radiation
| |
| | |
| survey, as required by the facility's
| |
| | |
| internal procedures, before opening the door. Twice, the operator placed one hand inside the irradiator
| |
| | |
| to retrieve the dosimeters.
| |
| | |
| Subsequently, the operator observed that the unit timer continued
| |
| | |
| to count, indicating
| |
| | |
| that the sources remained in the exposed position.
| |
| | |
| The operator checked his personal pocket dosimeter, but did not note an unusual reading. However, the operator did not report the incident until questioned
| |
| | |
| by the radiation
| |
| | |
| safety officer, who had noted an unusually
| |
| | |
| high dosimetry
| |
| | |
| report of 3.55 millisievert
| |
| | |
| (355 mrem) deep dose equivalent
| |
| | |
| for the worker. The dose to the right hand was calculated
| |
| | |
| to be a maximum of 12.5 millisievert
| |
| | |
| (1.25 rem).The design of the irradiator
| |
| | |
| includes two interconnected
| |
| | |
| interlock
| |
| | |
| systems, intended to prevent unshielded
| |
| | |
| exposure of the sources. These include a door interlock
| |
| | |
| system -- designed to allow opening of the shielded door only after the sources are placed in the fully shielded position -- and a source exposure-.
| |
| | |
| interlock
| |
| | |
| system -- designed to secure the sources in the fully shielded tDR FE E NO r/C9 03 ?C 0t, II
| |
| | |
| k k JI IN 96-35 June 11, 1996 position whenever the shielded door is open or unlocked.
| |
| | |
| The manufacturer
| |
| | |
| of the irradiator
| |
| | |
| indicated
| |
| | |
| that under normal operations, either system individually
| |
|
| |
|
| wouldiprevent
| | notice (IN)to alert addressees to two incidents where safety interlocks on |
|
| |
|
| inadvertent | | self-shielded irradiators (Category I) failed to prevent inadvertent exposure. |
|
| |
|
| access to the unshielded
| | The causes of these exposures stemmed from a lack of appropriate maintenance |
|
| |
|
| sources.Following
| | and/or worker training. The incidents include a broken spring -- possibly |
|
| |
|
| the incident, the manufacturer | | causing malfunction of the safety interlock -- and a worker who intentionally |
|
| |
|
| of the irradiator
| | bypassed a safety interlock. It is expected that recipients will review the |
|
| |
|
| was requested
| | information for applicability to their facilities and consider actions, as |
|
| |
|
| to perform an onsite inspection | | appropriate, to avoid similar problems. However, suggestions contained in |
|
| |
|
| of the irradiator
| | this information notice are not NRC requirements; therefore, no specific |
|
| |
|
| and facilities.
| | action nor written response is required. |
|
| |
|
| During the inspection, the manufacturer
| | ==Description of Circumstances== |
| | The first incident occurred when an operator may have been able to open the |
|
| |
|
| noted: (1) the irradiator
| | shielded door of an irradiator with the sources in the exposed position. |
|
| |
|
| was located in an area that was not climate-controlled;
| | After irradiation of several pocket dosimeters, the operator opened the |
| (2) internal components
| |
|
| |
|
| of the irradiator | | shielded door of the irradiator to retrieve the dosimeters, but did not |
|
| |
|
| were in a degraded state;(3) maintenance
| | perform a radiation survey, as required by the facility's internal procedures, before opening the door. Twice, the operator placed one hand inside the |
|
| |
|
| of the irradiator
| | irradiator to retrieve the dosimeters. Subsequently, the operator observed |
|
| |
|
| had last been performed
| | that the unit timer continued to count, indicating that the sources remained |
|
| |
|
| approximately
| | in the exposed position. The operator checked his personal pocket dosimeter, but did not note an unusual reading. However, the operator did not report the |
|
| |
|
| 10 years ago; and (4) a return spring, integral to the source exposure safety interlock system, was broken. The manufacturer
| | incident until questioned by the radiation safety officer, who had noted an |
|
| |
|
| indicated
| | unusually high dosimetry report of 3.55 millisievert (355 mrem) deep dose |
|
| |
|
| that the lack of environmental
| | equivalent for the worker. The dose to the right hand was calculated to be a |
|
| |
|
| control may have accelerated
| | maximum of 12.5 millisievert (1.25 rem). |
|
| |
|
| the degradation | | The design of the irradiator includes two interconnected interlock systems, intended to prevent unshielded exposure of the sources. These include a door |
|
| |
|
| of the internal components | | interlock system -- designed to allow opening of the shielded door only after |
|
| |
|
| of the irradiator, and that the lack of periodic maintenance
| | the sources are placed in the fully shielded position -- and a source exposure-. |
|
| |
|
| of the irradiator
| | interlock system -- designed to secure the sources in the fully shielded |
|
| |
|
| may have contributed
| | tDR FEE NOr/C9 03 ?C 0t, II |
|
| |
|
| to the failure of the return spring.The broken return spring may have caused the source securing mechanism
| | k k JI |
|
| |
|
| of the source exposure interlock | | IN 96-35 June 11, 1996 position whenever the shielded door is open or unlocked. The manufacturer of |
|
| |
|
| system to malfunction, possibly allowing exposure of the sources after the shielded door was unlocked and opened. However, during the post-incident
| | the irradiator indicated that under normal operations, either system |
|
| |
|
| investigation, neither the manufacturer
| | individually wouldiprevent inadvertent access to the unshielded sources. |
|
| |
|
| nor the licensee were able to identify a failed component
| | Following the incident, the manufacturer of the irradiator was requested to |
|
| |
|
| of either interlock | | perform an onsite inspection of the irradiator and facilities. During the |
|
| |
|
| system that could have allowed the shielded door to be opened with the sources in the exposed position.
| | inspection, the manufacturer noted: |
| | (1) the irradiator was located in an area that was not climate- controlled; |
| | (2) internal components of the irradiator were in a degraded state; |
| | (3) maintenance of the irradiator had last been performed approximately |
|
| |
|
| The manufacturer
| | 10 years ago; and |
|
| |
|
| indicated
| | (4) a return spring, integral to the source exposure safety interlock |
|
| |
|
| that the design of the source exposure mechanism | | system, was broken. The manufacturer indicated that the lack of |
|
| |
|
| -- the operator must manually move the sources from the shielded to the exposed position with a lever -- would have provided the operator with a positive indication
| | environmental control may have accelerated the degradation of the |
|
| |
|
| of source position even if the interlock | | internal components of the irradiator, and that the lack of periodic |
|
| |
|
| systems failed.Source position would have been further provided by a series of green and red source position lights on the irradiator.
| | maintenance of the irradiator may have contributed to the failure of |
|
| |
|
| The operator's
| | the return spring. |
|
| |
|
| actions indicate either a lack of training on the proper functioning
| | The broken return spring may have caused the source securing mechanism of the |
|
| |
|
| and use of the irradiator, a lack of understanding
| | source exposure interlock system to malfunction, possibly allowing exposure of |
|
| |
|
| of the training provided, and/or a disregard
| | the sources after the shielded door was unlocked and opened. However, during |
|
| |
|
| for following
| | the post-incident investigation, neither the manufacturer nor the licensee |
|
| |
|
| the established
| | were able to identify a failed component of either interlock system that could |
|
| |
|
| operating
| | have allowed the shielded door to be opened with the sources in the exposed |
|
| |
|
| and safety procedures.
| | position. The manufacturer indicated that the design of the source exposure |
|
| |
|
| The operator indicated
| | mechanism -- the operator must manually move the sources from the shielded to |
|
| |
|
| that the timer continued
| | the exposed position with a lever -- would have provided the operator with a |
|
| |
|
| to count when the shielded door was opened. However, the manufacturer
| | positive indication of source position even if the interlock systems failed. |
|
| |
|
| reported that the timer automatically
| | Source position would have been further provided by a series of green and red |
|
| |
|
| activates
| | source position lights on the irradiator. |
|
| |
|
| whenever the source lever is manually moved to one of the two source exposed positions
| | The operator's actions indicate either a lack of training on the proper |
|
| |
|
| and the lever is fully engaged in the source slot, and stops counting as soon as the lever is moved from the fully engaged position. | | functioning and use of the irradiator, a lack of understanding of the training |
|
| |
|
| The fact that the timer continued
| | provided, and/or a disregard for following the established operating and |
|
| |
|
| to count indicates that the operator had not moved the sources from the fully exposed and engaged position. | | safety procedures. The operator indicated that the timer continued to count |
|
| |
|
| The licensee reported that the operator had been trained in the operation
| | when the shielded door was opened. However, the manufacturer reported that |
|
| |
|
| of the irradiator
| | the timer automatically activates whenever the source lever is manually moved |
|
| |
|
| and was listed as an authorized | | to one of the two source exposed positions and the lever is fully engaged in |
|
| |
|
| user, but that the irradiator
| | the source slot, and stops counting as soon as the lever is moved from the |
|
| |
|
| was used infrequently
| | fully engaged position. The fact that the timer continued to count indicates |
|
| |
|
| and that this was only the operator's
| | that the operator had not moved the sources from the fully exposed and engaged |
|
| |
|
| second use of the irradiator
| | position. The licensee reported that the operator had been trained in the |
|
| |
|
| since being trained.The second incident occurred when a maintenance
| | operation of the irradiator and was listed as an authorized user, but that the |
|
| |
|
| worker preparing
| | irradiator was used infrequently and that this was only the operator's second |
|
| |
|
| to perform maintenance
| | use of the irradiator since being trained. |
|
| |
|
| on an irradiator
| | The second incident occurred when a maintenance worker preparing to perform |
|
| |
|
| bypassed the irradiator | | maintenance on an irradiator bypassed the irradiator door interlock system to |
|
| |
|
| door interlock
| | observe movement of the inner irradiation chamber. The maintenance was being |
|
| |
|
| system to observe movement of the inner irradiation
| | K> |
| | IN 96-35 June 11, 1996 performed to correct previous maintenance that resulted in the irradiator not |
|
| |
|
| chamber. The maintenance
| | functioning properly. The maintenance worker was unaware that, although the |
|
| |
|
| was being
| | sources remained shielded during movement of the irradiation chamber from the |
|
| |
|
| K>IN 96-35 June 11, 1996 performed
| | load to irradiate position, high levels of radiation scatter would be present. |
|
| |
|
| to correct previous maintenance
| | The maintenance worker, upon hearing the in-room monitor alarm, immediately |
|
| |
|
| that resulted in the irradiator
| | returned the radiation chamber to the 'load' position (maximum shielding). |
|
| |
|
| not functioning
| | Although the maintenance worker was familiar with the operation of the |
|
| |
|
| properly.
| | irradiator and had been responsible for its maintenance for nearly 15 years, the worker apparently had not been given formal training on radiation safety |
|
| |
|
| The maintenance | | or the operation and maintenance of the irradiator. The maintenance worker |
|
| |
|
| worker was unaware that, although the sources remained shielded during movement of the irradiation
| | was not aware of the scatter radiation and assumed that since the sources were |
|
| |
|
| chamber from the load to irradiate
| | not directly exposed, radiation from the sources would be contained within the |
|
| |
|
| position, high levels of radiation
| | device. |
|
| |
|
| scatter would be present.The maintenance
| | During this incident, another worker, hired to perform contract maintenance on |
|
| |
|
| worker, upon hearing the in-room monitor alarm, immediately
| | the irradiator, was also in the room near the irradiator. Neither worker wore |
|
| |
|
| returned the radiation
| | dosimetry nor had any documented training in radiation safety. Therefore, their doses could only be calculated based on their recollection and were |
|
| |
|
| chamber to the 'load' position (maximum shielding).
| | estimated to both be approximately 4 microsievert (0.4 mrem) whole body. |
|
| |
|
| Although the maintenance
| | Discussion |
|
| |
|
| worker was familiar with the operation
| | Although neither incident resulted in doses in excess of regulatory limits, the doses received in both incidents were unnecessary and possibly could have |
|
| |
|
| of the irradiator
| | been avoided with proper training and routine equipment maintenance. A |
|
| |
|
| and had been responsible
| | similar incident in 1984, where a door interlock failed, resulted in the |
|
| |
|
| for its maintenance
| | operator being exposed to 222 terabequerel (6000 curies) of cesium-137. |
|
| |
|
| for nearly 15 years, the worker apparently
| | The first incident clearly demonstrates the need to perform appropriate |
|
| |
|
| had not been given formal training on radiation
| | maintenance on these types of units. Even though these units are designed |
|
| |
|
| safety or the operation | | with interlocks and safety features intended to prevent inadvertent exposures, the components of these systems depend on adequate maintenance to function |
|
| |
|
| and maintenance | | properly. Failure to properly maintain these systems and provide appropriate |
|
| |
|
| of the irradiator. | | training could result in unnecessary exposures. Manufacturers of these types |
|
| |
|
| The maintenance
| | of irradiators frequently provide initial and periodic training on the |
|
| |
|
| worker was not aware of the scatter radiation
| | operation of their units and, in some cases, training on other manufacturers' |
| | units, as well. Initial training is typically a condition of the license and, therefore, must be provided to all irradiator users and maintenance personnel. |
|
| |
|
| and assumed that since the sources were not directly exposed, radiation
| | Periodic refresher training is also beneficial as a reminder for working |
|
| |
|
| from the sources would be contained
| | safely around the irradiator and provides for a means to receive or |
|
| |
|
| within the device.During this incident, another worker, hired to perform contract maintenance
| | disseminate additional or updated information. |
|
| |
|
| on the irradiator, was also in the room near the irradiator.
| | In addition, most manufacturers have a recommended schedule of maintenance |
|
| |
|
| Neither worker wore dosimetry
| | and/or recommended preventative/periodic maintenance that should be performed. |
|
| |
|
| nor had any documented
| | Users of these types of irradiators should evaluate their usage to determine |
|
| |
|
| training in radiation
| | the applicability of the recommended maintenance to their situation and usage. |
|
| |
|
| safety. Therefore, their doses could only be calculated
| | Users who operate their unit more than usual or who use their units under |
|
| |
|
| based on their recollection
| | harsh conditions should consider the need for stepped-up maintenance or |
|
| |
|
| and were estimated
| | '-> IN 96-35 June 11, 1996 shortened maintenance intervals. In addition, each manufacturer's recommended |
|
| |
|
| to both be approximately | | maintenance may vary according to the specific unit or type of use. |
|
| |
|
| 4 microsievert
| | Therefore, personis performing maintenance on their unit may require specific |
|
| |
|
| (0.4 mrem) whole body.Discussion
| | maintenance training for their unit. |
|
| |
|
| Although neither incident resulted in doses in excess of regulatory
| | Users who are not aware of the required training for their unit, or who wish |
|
| |
|
| limits, the doses received in both incidents
| | to receive information concerning training in general, should consult their |
|
| |
|
| were unnecessary
| | license, licensing authority, or the manufacturer of the unit. Regulatory |
|
| |
|
| and possibly could have been avoided with proper training and routine equipment | | Guide 10.9, provides additional guidance in this area and may assist persons |
|
| |
|
| maintenance. | | who wish to develop a training and maintenance program. Users who wish to |
|
| |
|
| A similar incident in 1984, where a door interlock
| | receive additional information concerning recommended maintenance for their |
|
| |
|
| failed, resulted in the operator being exposed to 222 terabequerel
| | unit should contact the manufacturer of the unit. In addition, third-party |
|
| |
|
| (6000 curies) of cesium-137.
| | service companies may also be available for training and maintenance services |
|
| |
|
| The first incident clearly demonstrates
| | for these types of irradiators. |
|
| |
|
| the need to perform appropriate
| | This information notice requires no specific action nor written response. If |
|
| |
|
| maintenance
| | you have any questions about the information in this notice, please contact |
|
| |
|
| on these types of units. Even though these units are designed with interlocks
| | one of the technical contacts listed below or the appropriate regional office. |
|
| |
|
| and safety features intended to prevent inadvertent
| | I3W¶flstn 8 by9WWstIA |
|
| |
|
| exposures, the components
| | Donald A. Cool, Director |
|
| |
|
| of these systems depend on adequate maintenance | | Division of Industrial and |
|
| |
|
| to function properly.
| | Medical Nuclear Safety |
|
| |
|
| Failure to properly maintain these systems and provide appropriate
| | Office of Nuclear Material Safety |
|
| |
|
| training could result in unnecessary
| | and Safeguards |
|
| |
|
| exposures.
| | Technical contacts: Douglas Broaddus, NMSS |
|
| |
|
| Manufacturers
| | (301) 415-5847 Internet:dab~nrc.gov |
|
| |
|
| of these types of irradiators
| | Anthony Kirkwood, NMSS |
|
| |
|
| frequently
| | (301) 415-6140 |
| | | Internet:ask~nrc.gov |
| provide initial and periodic training on the operation
| |
| | |
| of their units and, in some cases, training on other manufacturers'
| |
| units, as well. Initial training is typically
| |
| | |
| a condition
| |
| | |
| of the license and, therefore, must be provided to all irradiator
| |
| | |
| users and maintenance
| |
| | |
| personnel.
| |
| | |
| Periodic refresher
| |
| | |
| training is also beneficial
| |
| | |
| as a reminder for working safely around the irradiator
| |
| | |
| and provides for a means to receive or disseminate
| |
| | |
| additional
| |
| | |
| or updated information.
| |
| | |
| In addition, most manufacturers
| |
| | |
| have a recommended
| |
| | |
| schedule of maintenance
| |
| | |
| and/or recommended
| |
| | |
| preventative/periodic
| |
| | |
| maintenance
| |
| | |
| that should be performed.
| |
| | |
| Users of these types of irradiators
| |
| | |
| should evaluate their usage to determine the applicability
| |
| | |
| of the recommended
| |
| | |
| maintenance
| |
| | |
| to their situation
| |
| | |
| and usage.Users who operate their unit more than usual or who use their units under harsh conditions
| |
| | |
| should consider the need for stepped-up
| |
| | |
| maintenance
| |
| | |
| or
| |
| | |
| '-> IN 96-35 June 11, 1996 shortened
| |
| | |
| maintenance
| |
| | |
| intervals.
| |
| | |
| In addition, each manufacturer's
| |
| | |
| recommended
| |
| | |
| maintenance
| |
| | |
| may vary according
| |
| | |
| to the specific unit or type of use.Therefore, personis performing
| |
| | |
| maintenance
| |
| | |
| on their unit may require specific maintenance
| |
| | |
| training for their unit.Users who are not aware of the required training for their unit, or who wish to receive information
| |
| | |
| concerning
| |
| | |
| training in general, should consult their license, licensing
| |
| | |
| authority, or the manufacturer
| |
| | |
| of the unit. Regulatory
| |
| | |
| Guide 10.9, provides additional
| |
| | |
| guidance in this area and may assist persons who wish to develop a training and maintenance
| |
| | |
| program. Users who wish to receive additional
| |
| | |
| information
| |
| | |
| concerning
| |
| | |
| recommended
| |
| | |
| maintenance
| |
| | |
| for their unit should contact the manufacturer
| |
| | |
| of the unit. In addition, third-party
| |
| | |
| service companies
| |
| | |
| may also be available
| |
| | |
| for training and maintenance
| |
| | |
| services for these types of irradiators.
| |
| | |
| This information
| |
| | |
| notice requires no specific action nor written response.
| |
| | |
| If you have any questions
| |
| | |
| about the information
| |
| | |
| in this notice, please contact one of the technical
| |
| | |
| contacts listed below or the appropriate
| |
| | |
| regional office.I3W¶flstn 8 by9WWstIA Donald A. Cool, Director Division of Industrial
| |
| | |
| and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
| |
| | |
| Technical
| |
| | |
| contacts:
| |
| Douglas Broaddus, NMSS (301) 415-5847 Internet:dab~nrc.gov
| |
| | |
| Anthony Kirkwood, NMSS (301) 415-6140 Internet:ask~nrc.gov
| |
|
| |
|
| Attachments: | | Attachments: |
| 1. List of Recently issued NMSS Information | | 1. List of Recently issued NMSS Information Notices |
| | |
| Notices 2. List of Recently issued NRC Information | |
| | |
| Notices DOCUMENT NAME: 96-35.IN To receive a copy of this document, Indicate In the box: C' = Copy without attachment/enclosure
| |
|
| |
|
| *E' -Copy with attachmentjendosure
| | 2. List of Recently issued NRC Information Notices |
|
| |
|
| N
| | DOCUMENT NAME: 96-35.IN |
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| |
|
| * No copy* See previous concurrence
| | To receive a copy of this document, Indicate In the box: C' = Copy without attachment/enclosure *E' - Copy with attachmentjendosure N |
|
| |
|
| OFFICE IIMAB* [ClIMAB* [C Tech Editor* l IMOB* [C IMNS* I C, NAME IDBroaddus*
| | * No copy |
| LCamper lEKraus _KRamsey jDCof'DATE 14/17/96 5/28/96 4/01/96 5/31/96 6/4 96 11 OFFICIAL RECORD COPY
| |
|
| |
|
| j;IN 96-XX May XX, 1996 Users who are not aware of the required training for their unit, or who wish to receive information
| | * See previous concurrence |
|
| |
|
| concerning
| | OFFICE IIMAB* [ClIMAB* [C Tech Editor* l IMOB* [C IMNS* I C, |
| | NAME IDBroaddus* LCamper lEKraus _KRamsey jDCof' |
| | DATE 14/17/96 5/28/96 4/01/96 5/31/96 6/4 96 11 OFFICIAL RECORD COPY |
|
| |
|
| training in general, should consult their license, licensing
| | j; |
| | IN 96-XX |
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| |
|
| authority, or the manufacturer
| | May XX, 1996 Users who are not aware of the required training for their unit, or who wish |
|
| |
|
| of the unit. Regulatory
| | to receive information concerning training in general, should consult their |
|
| |
|
| Guide 10.9, provides additional
| | license, licensing authority, or the manufacturer of the unit. Regulatory |
|
| |
|
| guidance in this area and may assist persons who wish to develop a training and maintenance | | Guide 10.9, provides additional guidance in this area and may assist persons |
|
| |
|
| program. Users who wish to receive additional | | who wish to develop a training and maintenance program. Users who wish to |
|
| |
|
| information | | receive additional information concerning recommended maintenance for their |
|
| |
|
| concerning
| | unit should contact the manufacturer of the unit. In addition, third-party |
|
| |
|
| recommended
| | service companies may also be available for training and maintenance services |
|
| |
|
| maintenance
| | for these types of irradiators. |
|
| |
|
| for their unit should contact the manufacturer
| | This information notice requires no specific action nor written response. If |
|
| |
|
| of the unit. In addition, third-party
| | you have any questions about the information in this notice, please contact |
|
| |
|
| service companies
| | one of the technical contacts listed below or the appropriate regional office. |
|
| |
|
| may also be available
| | Donald A. Cool, Director |
|
| |
|
| for training and maintenance
| | Division of Industrial and |
|
| |
|
| services for these types of irradiators.
| | Medical Nuclear Safety |
|
| |
|
| This information
| | Office of Nuclear Material Safety |
|
| |
|
| notice requires no specific action nor written response.
| | and Safeguards |
|
| |
|
| If you have any questions
| | Technical contacts: Douglas Broaddus, NMSS |
|
| |
|
| about the information
| | (301) 415-5847 Anthony Kirkwood, NMSS |
|
| |
|
| in this notice, please contact one of the technical
| | (301) 415-6140 |
| | Attachments: |
| | 1. List of Recently issued NMSS Information Notices |
|
| |
|
| contacts listed below or the appropriate
| | 2. List of Recently issued NRC Information Notices |
|
| |
|
| regional office.Donald A. Cool, Director Division of Industrial
| | DOCUMENT NAME: A:\IRADIATR.FIN |
|
| |
|
| and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
| | To receive a copy of this docunent, Indicate hI the box: 'C Copy without attachmentlenclosure WE-= Copy with attachmentlenclosure ONE copY |
|
| |
|
| Technical
| | * See previous concurrence a |
|
| |
|
| contacts:
| | OFFICE IMAB I INAB 15 /HTech Editor I IMOB IMN h |
| Douglas Broaddus, NMSS (301) 415-5847 Anthony Kirkwood, NMSS (301) 415-6140 Attachments:
| |
| 1. List of Recently issued NMSS Information
| |
|
| |
|
| Notices 2. List of Recently issued NRC Information
| | NAME DBroaddus* LCam er' 1EKraus* KRamse Kmfl Co |
|
| |
|
| Notices DOCUMENT NAME: A:\IRADIATR.FIN
| | DATE 4/17/96 L/46/96 14/01/96 5-13j /96 / |
| | OFFICIAL RECORD COPY |
|
| |
|
| To receive a copy of this docunent, Indicate hI the box: 'C Copy without attachmentlenclosure
| | IN 96-XX |
|
| |
|
| WE- = Copy with attachmentlenclosure
| | May XX, 1996 Users who are not aware of the required training for their unit, or who wish |
|
| |
|
| ONE copY* See previous concurrence
| | to receive information concerning training in general, should consult their |
|
| |
|
| a OFFICE IMAB I INAB 15 /HTech Editor I IMOB IMN h NAME DBroaddus*
| | license, licensing authority, or the manufacturer of the unit. Regulatory |
| LCam er' 1EKraus* KRamse Kmfl Co DATE 4/17/96 L/46/96 14/01/96 5-13j /96 /OFFICIAL RECORD COPY
| |
|
| |
|
| IN 96-XX May XX, 1996 Users who are not aware of the required training for their unit, or who wish to receive information
| | Guide 10.9, provides additional guidance in this area and may assist persons |
|
| |
|
| concerning
| | who wish to develop a training and maintenance program. Users who wish to |
|
| |
|
| training in general, should consult their license, licensing
| | receive additional information concerning recommended maintenance for their |
|
| |
|
| authority, or the manufacturer
| | unit should contact the manufacturer of the unit. In addition, third-party |
|
| |
|
| of the unit. Regulatory
| | service companies may also be available for training and maintenance services |
|
| |
|
| Guide 10.9, provides additional
| | for these types of irradiators. |
|
| |
|
| guidance in this area and may assist persons who wish to develop a training and maintenance
| | This information notice requires no specific action nor written response. If |
|
| |
|
| program. Users who wish to receive additional
| | you have any questions about the information in this notice, please contact |
|
| |
|
| information
| | one of the technical contacts listed below or the appropriate regional office. |
|
| |
|
| concerning
| | Donald A. Cool, Director |
| | |
| recommended
| |
| | |
| maintenance
| |
| | |
| for their unit should contact the manufacturer
| |
| | |
| of the unit. In addition, third-party
| |
| | |
| service companies
| |
| | |
| may also be available
| |
| | |
| for training and maintenance
| |
| | |
| services for these types of irradiators.
| |
| | |
| This information
| |
| | |
| notice requires no specific action nor written response.
| |
| | |
| If you have any questions
| |
| | |
| about the information
| |
| | |
| in this notice, please contact one of the technical
| |
| | |
| contacts listed below or the appropriate
| |
| | |
| regional office.Donald A. Cool, Director Division of Industrial
| |
| | |
| and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
| |
| | |
| Technical
| |
| | |
| contacts:
| |
| Douglas Broaddus, NMSS 301-415-5847 Anthony Kirkwood, RI 610-337-5050
| |
| Attachments:
| |
| 1. List of Recently issued NMSS Information
| |
|
| |
|
| Notices 2. List of Recently issued NRC Information
| | Division of Industrial and |
|
| |
|
| Notices DOCUMENT NAME: A:\IRADIATR.FIN
| | Medical Nuclear Safety |
|
| |
|
| To receiv a copy of this document, Indicate In the box: C' = Copy without attachmentlenclosure
| | Office of Nuclear Material Safety |
|
| |
|
| 'E' = Copy with aftachment/enclosure
| | and Safeguards |
|
| |
|
| *'N -No copy lOFFICE IMAB [ IMAB LJTech Editor LAL IMOB LJIMNS INAME DBroaddus
| | Technical contacts: Douglas Broaddus, NMSS |
|
| |
|
| LCamper EKraus wa KRamsey DCool DMTE 4//f/96 4/ /96 4/W /96 4/ /96 4/ /96 OFFICIAL RECORD COPY
| | 301-415-5847 Anthony Kirkwood, RI |
|
| |
|
| KUJ KU Attachment
| | 610-337-5050 |
| | Attachments: |
| | 1. List of Recently issued NMSS Information Notices |
|
| |
|
| 1 IN 96-35 June 11, 1996 LIST OF RECENTLY ISSUED NMSS INFORMATION
| | 2. List of Recently issued NRC Information Notices |
|
| |
|
| NOTICES Information
| | DOCUMENT NAME: A:\IRADIATR.FIN |
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| |
|
| ' Date of Notice No. Subject Issuance Issued to 96-33 Erroneous | | To receiv a copy of this document, Indicate In the box: C' = Copy without attachmentlenclosure 'E' = Copy with aftachment/enclosure *'N - No copy |
|
| |
|
| Data from Defec-tive Thermocouple
| | lOFFICE IMAB [ IMAB LJTech Editor LAL IMOB LJIMNS |
|
| |
|
| Results in a Fire 05/224/96 All material and fuel cycle licensees
| | INAME DBroaddus LCamper EKraus wa KRamsey DCool |
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| |
|
| that monitor tem-perature with thermocouples
| | DMTE 4//f/96 4/ /96 4/W /96 4/ /96 4/ /96 OFFICIAL RECORD COPY |
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| |
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| 96-28 96-21 96-20 96-18 Suggested
| | KUJ KU |
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| |
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| Guidance Relat-ing to Development
| | Attachment 1 IN 96-35 June 11, 1996 LIST OF RECENTLY ISSUED |
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| and Implementation
| | NMSS INFORMATION NOTICES |
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| of Correc-tive Action Safety Concerns Related to the Design of the Door Interlock | | Information ' Date of |
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| Circuit on Nucletron
| | Notice No. Subject Issuance Issued to |
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| |
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| High-Dose
| | 96-33 Erroneous Data from Defec- 05/224/96 All material and fuel cycle |
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| Rate and Pulsed Dose Rate Remote Afterloading
| | tive Thermocouple Results licensees that monitor tem- in a Fire perature with thermocouples |
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| Brachy-therapy Devices Demonstration
| | 96-28 Suggested Guidance Relat- 05/01/96 All material and fuel cycle |
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| of Associ-ated Equipment
| | ing to Development and licensees |
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| Compliance
| | Implementation of Correc- tive Action |
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| with 10 CFR 34.20 Compliance
| | 96-21 Safety Concerns Related 04/10/96 All NRC Medical Licensees |
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| With 10 CFR Part 20 for Airborne Thorium Incident Reporting Requirements
| | to the Design of the Door authorized to use brachy- Interlock Circuit on therapy sources in high- Nucletron High-Dose Rate and pulsed-dose-rate remote |
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| for Radiography
| | and Pulsed Dose Rate |
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| |
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| Licensees 10 CFR 34.20; Final Effective
| | Remote Afterloading Brachy- therapy Devices |
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| |
|
| ===Date Handling Uncontained===
| | 96-20 Demonstration of Associ- 04/04/96 All industrial radiography |
| Yellowcake
| |
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| |
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| Outside of a Facility Processing
| | ated Equipment Compliance licensees and radiography |
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| |
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| Circuit Recent Incidents
| | with 10 CFR 34.20 equipment manufacturers |
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| Involving Potential
| | 96-18 Compliance With 10 CFR 03/25/96 All material licensees |
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| Loss of Control of Licensed Material 05/01/96 04/10/96 04/04/96 03/25/96 01/10/96 12/18/95 12/6/95 10/27/95 All material and fuel cycle licensees All NRC Medical Licensees authorized
| | Part 20 for Airborne authorized to possess and |
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| to use brachy-therapy sources in high-and pulsed-dose-rate
| | Thorium use thorium in unsealed form |
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| remote All industrial
| | 96-04 Incident Reporting 01/10/96 All Radiography Licensees |
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| radiography
| | Requirements for and Manufacturers of |
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| licensees
| | Radiography Licensees Radiography Equipment |
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| and radiography
| | 95-58 10 CFR 34.20; Final 12/18/95 Industrial Radiography |
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| equipment
| | Effective Date Licensees. |
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| |
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| manufacturers
| | 95-55 Handling Uncontained 12/6/95 All Uranium Recovery |
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| All material licensees authorized
| | Yellowcake Outside of a Licensees. |
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| to possess and use thorium in unsealed form All Radiography
| | Facility Processing Circuit |
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| Licensees and Manufacturers
| | 95-51 Recent Incidents Involving 10/27/95 All material and fuel cycle |
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| of Radiography | | Potential Loss of Control licensees. |
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| Equipment Industrial
| | of Licensed Material |
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| Radiography
| | K>- iKJ |
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| |
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| Licensees.
| | Attachment 2 IN 96-35 June 11, 1996 LIST OF RECENTLY ISSUED |
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| All Uranium Recovery Licensees.
| | NRC INFORMATION NOTICES |
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| |
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| All material and fuel cycle licensees.
| | Information Date of |
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| |
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| 96-04 95-58 95-55 95-51 K> -iKJ Attachment
| | Notice No. Subject Issuance Issued to |
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| |
|
| 2 IN 96-35 June 11, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
| | 96-34 Hydrogen Gas Ignition 05/31/96 All holders of OLs or CPs |
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| |
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| NOTICES Information
| | during Closure Welding for nuclear power reactors |
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| |
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| Date of Notice No. Subject Issuance Issued to 96-34 96-33 96-32 96-31 96-30 Hydrogen Gas Ignition during Closure Welding of a VSC-24 Multi-Assembly
| | of a VSC-24 Multi-Assembly |
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| |
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| Sealed Basket Erroneous | | Sealed Basket |
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| Data From Defective | | 96-33 Erroneous Data From 05/24/96 All material and fuel cycle |
|
| |
|
| ===Thermocouple===
| | Defective Thermocouple licensees that monitor tem- Results in a Fire perature with thermocouples |
| Results in a Fire Implementation | |
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| |
|
| of 10 CFR 50.55a(g)(6)(ii)(A),"Augmented | | 96-32 Implementation of 10 CFR 06/05/96 All holders of OLs or CPs |
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| Examination
| | 50.55a(g)(6)(ii)(A), for nuclear power reactors |
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| |
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| of Reactor Vessel" Cross-Tied
| | "Augmented Examination |
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| |
|
| Safety Injec-tion Accumulators | | of Reactor Vessel" |
| | 96-31 Cross-Tied Safety Injec- 05/22/96 All holders of OLs or CPs |
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| Inaccuracy
| | tion Accumulators for pressurized water |
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| |
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| of Diagnostic
| | reactors |
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| |
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| Equipment
| | 96-30 Inaccuracy of Diagnostic 05/21/96 All holders of OLs or CPs |
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| |
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| for Motor-Operated Butterfly | | Equipment for Motor- for nuclear power reactors |
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| |
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| Valves Requirements | | Operated Butterfly Valves |
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| |
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| in 10 CFR Part 21 for Reporting | | 96-29 Requirements in 10 CFR 05/20/96 All holders of OLs or CPs |
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| and Evaluating | | Part 21 for Reporting and for nuclear power reactors |
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| |
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| Software Errors Suggested | | Evaluating Software Errors |
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| |
|
| Guidance Relating to Development | | 96-28 Suggested Guidance Relating 05/01/96 All material and fuel cycle |
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| |
|
| and Imple-mentation | | to Development and Imple- licensees |
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| |
|
| of Corrective | | mentation of Corrective |
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| |
|
| Action Potential | | Action |
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| |
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| Clogging of High Pressure Safety Injection Throttle Valves During Recirculation | | 96-27 Potential Clogging of High 05/01/96 All holders of OLs or CPs |
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| |
|
| Recent Problems with Over-head Cranes Transversing
| | Pressure Safety Injection for pressurized water |
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| |
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| In-Core Probe Overwithdrawn
| | Throttle Valves During reactors |
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| |
|
| at LaSalle County Station, Unit 1 05/31/96 05/24/96 06/05/96 05/22/96 05/21/96 05/20/96 05/01/96 05/01/96 04/30/96 04/30/96 All holders of OLs or CPs for nuclear power reactors All material and fuel cycle licensees
| | Recirculation |
|
| |
|
| that monitor tem-perature with thermocouples
| | 96-26 Recent Problems with Over- 04/30/96 All holders of OLs or CPs |
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| |
|
| All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for pressurized
| | head Cranes for nuclear power reactors |
|
| |
|
| water reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All material and fuel cycle licensees All holders of OLs or CPs for pressurized
| | 96-25 Transversing In-Core Probe 04/30/96 All holders of OLs or CPs |
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| |
|
| water reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors 96-29 96-28 96-27 96-26 96-25 OL -Operating
| | Overwithdrawn at LaSalle for nuclear power reactors |
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| |
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| License CP -Construction | | County Station, Unit 1 OL - Operating License |
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| |
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| Permit}} | | CP - Construction Permit}} |
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| |
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and TrainingML031060046 |
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, 05000442, 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: |
06/11/1996 |
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From: |
Cool D NRC/NMSS/IMNS |
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To: |
|
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References |
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IN-96-035, NUDOCS 9606060078 |
Download: ML031060046 (8) |
|
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, 05000442, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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 [[:05000442]] 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 [[:05000442]] 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 June 11, 1996 NRC INFORMATION NOTICE 96-35: FAILURE OF SAFETY SYSTEMS ON SELF-SHIELDED
IRRADIATORS BECAUSE OF INADEQUATE MAINTENANCE
AND TRAINING
Addressees
All U.S. Nuclear Regulatory Commission irradiator licensees and vendors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice (IN)to alert addressees to two incidents where safety interlocks on
self-shielded irradiators (Category I) failed to prevent inadvertent exposure.
The causes of these exposures stemmed from a lack of appropriate maintenance
and/or worker training. The incidents include a broken spring -- possibly
causing malfunction of the safety interlock -- and a worker who intentionally
bypassed a safety interlock. 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 NRC requirements; therefore, no specific
action nor written response is required.
Description of Circumstances
The first incident occurred when an operator may have been able to open the
shielded door of an irradiator with the sources in the exposed position.
After irradiation of several pocket dosimeters, the operator opened the
shielded door of the irradiator to retrieve the dosimeters, but did not
perform a radiation survey, as required by the facility's internal procedures, before opening the door. Twice, the operator placed one hand inside the
irradiator to retrieve the dosimeters. Subsequently, the operator observed
that the unit timer continued to count, indicating that the sources remained
in the exposed position. The operator checked his personal pocket dosimeter, but did not note an unusual reading. However, the operator did not report the
incident until questioned by the radiation safety officer, who had noted an
unusually high dosimetry report of 3.55 millisievert (355 mrem) deep dose
equivalent for the worker. The dose to the right hand was calculated to be a
maximum of 12.5 millisievert (1.25 rem).
The design of the irradiator includes two interconnected interlock systems, intended to prevent unshielded exposure of the sources. These include a door
interlock system -- designed to allow opening of the shielded door only after
the sources are placed in the fully shielded position -- and a source exposure-.
interlock system -- designed to secure the sources in the fully shielded
tDR FEE NOr/C9 03 ?C 0t, II
k k JI
IN 96-35 June 11, 1996 position whenever the shielded door is open or unlocked. The manufacturer of
the irradiator indicated that under normal operations, either system
individually wouldiprevent inadvertent access to the unshielded sources.
Following the incident, the manufacturer of the irradiator was requested to
perform an onsite inspection of the irradiator and facilities. During the
inspection, the manufacturer noted:
(1) the irradiator was located in an area that was not climate- controlled;
(2) internal components of the irradiator were in a degraded state;
(3) maintenance of the irradiator had last been performed approximately
10 years ago; and
(4) a return spring, integral to the source exposure safety interlock
system, was broken. The manufacturer indicated that the lack of
environmental control may have accelerated the degradation of the
internal components of the irradiator, and that the lack of periodic
maintenance of the irradiator may have contributed to the failure of
the return spring.
The broken return spring may have caused the source securing mechanism of the
source exposure interlock system to malfunction, possibly allowing exposure of
the sources after the shielded door was unlocked and opened. However, during
the post-incident investigation, neither the manufacturer nor the licensee
were able to identify a failed component of either interlock system that could
have allowed the shielded door to be opened with the sources in the exposed
position. The manufacturer indicated that the design of the source exposure
mechanism -- the operator must manually move the sources from the shielded to
the exposed position with a lever -- would have provided the operator with a
positive indication of source position even if the interlock systems failed.
Source position would have been further provided by a series of green and red
source position lights on the irradiator.
The operator's actions indicate either a lack of training on the proper
functioning and use of the irradiator, a lack of understanding of the training
provided, and/or a disregard for following the established operating and
safety procedures. The operator indicated that the timer continued to count
when the shielded door was opened. However, the manufacturer reported that
the timer automatically activates whenever the source lever is manually moved
to one of the two source exposed positions and the lever is fully engaged in
the source slot, and stops counting as soon as the lever is moved from the
fully engaged position. The fact that the timer continued to count indicates
that the operator had not moved the sources from the fully exposed and engaged
position. The licensee reported that the operator had been trained in the
operation of the irradiator and was listed as an authorized user, but that the
irradiator was used infrequently and that this was only the operator's second
use of the irradiator since being trained.
The second incident occurred when a maintenance worker preparing to perform
maintenance on an irradiator bypassed the irradiator door interlock system to
observe movement of the inner irradiation chamber. The maintenance was being
K>
IN 96-35 June 11, 1996 performed to correct previous maintenance that resulted in the irradiator not
functioning properly. The maintenance worker was unaware that, although the
sources remained shielded during movement of the irradiation chamber from the
load to irradiate position, high levels of radiation scatter would be present.
The maintenance worker, upon hearing the in-room monitor alarm, immediately
returned the radiation chamber to the 'load' position (maximum shielding).
Although the maintenance worker was familiar with the operation of the
irradiator and had been responsible for its maintenance for nearly 15 years, the worker apparently had not been given formal training on radiation safety
or the operation and maintenance of the irradiator. The maintenance worker
was not aware of the scatter radiation and assumed that since the sources were
not directly exposed, radiation from the sources would be contained within the
device.
During this incident, another worker, hired to perform contract maintenance on
the irradiator, was also in the room near the irradiator. Neither worker wore
dosimetry nor had any documented training in radiation safety. Therefore, their doses could only be calculated based on their recollection and were
estimated to both be approximately 4 microsievert (0.4 mrem) whole body.
Discussion
Although neither incident resulted in doses in excess of regulatory limits, the doses received in both incidents were unnecessary and possibly could have
been avoided with proper training and routine equipment maintenance. A
similar incident in 1984, where a door interlock failed, resulted in the
operator being exposed to 222 terabequerel (6000 curies) of cesium-137.
The first incident clearly demonstrates the need to perform appropriate
maintenance on these types of units. Even though these units are designed
with interlocks and safety features intended to prevent inadvertent exposures, the components of these systems depend on adequate maintenance to function
properly. Failure to properly maintain these systems and provide appropriate
training could result in unnecessary exposures. Manufacturers of these types
of irradiators frequently provide initial and periodic training on the
operation of their units and, in some cases, training on other manufacturers'
units, as well. Initial training is typically a condition of the license and, therefore, must be provided to all irradiator users and maintenance personnel.
Periodic refresher training is also beneficial as a reminder for working
safely around the irradiator and provides for a means to receive or
disseminate additional or updated information.
In addition, most manufacturers have a recommended schedule of maintenance
and/or recommended preventative/periodic maintenance that should be performed.
Users of these types of irradiators should evaluate their usage to determine
the applicability of the recommended maintenance to their situation and usage.
Users who operate their unit more than usual or who use their units under
harsh conditions should consider the need for stepped-up maintenance or
'-> IN 96-35 June 11, 1996 shortened maintenance intervals. In addition, each manufacturer's recommended
maintenance may vary according to the specific unit or type of use.
Therefore, personis performing maintenance on their unit may require specific
maintenance training for their unit.
Users who are not aware of the required training for their unit, or who wish
to receive information concerning training in general, should consult their
license, licensing authority, or the manufacturer of the unit. Regulatory
Guide 10.9, provides additional guidance in this area and may assist persons
who wish to develop a training and maintenance program. Users who wish to
receive additional information concerning recommended maintenance for their
unit should contact the manufacturer of the unit. In addition, third-party
service companies may also be available for training and maintenance services
for these types of irradiators.
This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate regional office.
I3W¶flstn 8 by9WWstIA
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Douglas Broaddus, NMSS
(301) 415-5847 Internet:dab~nrc.gov
Anthony Kirkwood, NMSS
(301) 415-6140
Internet:ask~nrc.gov
Attachments:
1. List of Recently issued NMSS Information Notices
2. List of Recently issued NRC Information Notices
DOCUMENT NAME: 96-35.IN
To receive a copy of this document, Indicate In the box: C' = Copy without attachment/enclosure *E' - Copy with attachmentjendosure N
OFFICE IIMAB* [ClIMAB* [C Tech Editor* l IMOB* [C IMNS* I C,
NAME IDBroaddus* LCamper lEKraus _KRamsey jDCof'
DATE 14/17/96 5/28/96 4/01/96 5/31/96 6/4 96 11 OFFICIAL RECORD COPY
j;
IN 96-XX
May XX, 1996 Users who are not aware of the required training for their unit, or who wish
to receive information concerning training in general, should consult their
license, licensing authority, or the manufacturer of the unit. Regulatory
Guide 10.9, provides additional guidance in this area and may assist persons
who wish to develop a training and maintenance program. Users who wish to
receive additional information concerning recommended maintenance for their
unit should contact the manufacturer of the unit. In addition, third-party
service companies may also be available for training and maintenance services
for these types of irradiators.
This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Douglas Broaddus, NMSS
(301) 415-5847 Anthony Kirkwood, NMSS
(301) 415-6140
Attachments:
1. List of Recently issued NMSS Information Notices
2. List of Recently issued NRC Information Notices
DOCUMENT NAME: A:\IRADIATR.FIN
To receive a copy of this docunent, Indicate hI the box: 'C Copy without attachmentlenclosure WE-= Copy with attachmentlenclosure ONE copY
- See previous concurrence a
OFFICE IMAB I INAB 15 /HTech Editor I IMOB IMN h
NAME DBroaddus* LCam er' 1EKraus* KRamse Kmfl Co
DATE 4/17/96 L/46/96 14/01/96 5-13j /96 /
OFFICIAL RECORD COPY
IN 96-XX
May XX, 1996 Users who are not aware of the required training for their unit, or who wish
to receive information concerning training in general, should consult their
license, licensing authority, or the manufacturer of the unit. Regulatory
Guide 10.9, provides additional guidance in this area and may assist persons
who wish to develop a training and maintenance program. Users who wish to
receive additional information concerning recommended maintenance for their
unit should contact the manufacturer of the unit. In addition, third-party
service companies may also be available for training and maintenance services
for these types of irradiators.
This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Douglas Broaddus, NMSS
301-415-5847 Anthony Kirkwood, RI
610-337-5050
Attachments:
1. List of Recently issued NMSS Information Notices
2. List of Recently issued NRC Information Notices
DOCUMENT NAME: A:\IRADIATR.FIN
To receiv a copy of this document, Indicate In the box: C' = Copy without attachmentlenclosure 'E' = Copy with aftachment/enclosure *'N - No copy
lOFFICE IMAB [ IMAB LJTech Editor LAL IMOB LJIMNS
INAME DBroaddus LCamper EKraus wa KRamsey DCool
DMTE 4//f/96 4/ /96 4/W /96 4/ /96 4/ /96 OFFICIAL RECORD COPY
KUJ KU
Attachment 1 IN 96-35 June 11, 1996 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information ' Date of
Notice No. Subject Issuance Issued to
96-33 Erroneous Data from Defec- 05/224/96 All material and fuel cycle
tive Thermocouple Results licensees that monitor tem- in a Fire perature with thermocouples
96-28 Suggested Guidance Relat- 05/01/96 All material and fuel cycle
ing to Development and licensees
Implementation of Correc- tive Action
96-21 Safety Concerns Related 04/10/96 All NRC Medical Licensees
to the Design of the Door authorized to use brachy- Interlock Circuit on therapy sources in high- Nucletron High-Dose Rate and pulsed-dose-rate remote
and Pulsed Dose Rate
Remote Afterloading Brachy- therapy Devices
96-20 Demonstration of Associ- 04/04/96 All industrial radiography
ated Equipment Compliance licensees and radiography
with 10 CFR 34.20 equipment manufacturers
96-18 Compliance With 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed form
96-04 Incident Reporting 01/10/96 All Radiography Licensees
Requirements for and Manufacturers of
Radiography Licensees Radiography Equipment
95-58 10 CFR 34.20; Final 12/18/95 Industrial Radiography
Effective Date Licensees.
95-55 Handling Uncontained 12/6/95 All Uranium Recovery
Yellowcake Outside of a Licensees.
Facility Processing Circuit
95-51 Recent Incidents Involving 10/27/95 All material and fuel cycle
Potential Loss of Control licensees.
of Licensed Material
K>- iKJ
Attachment 2 IN 96-35 June 11, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-34 Hydrogen Gas Ignition 05/31/96 All holders of OLs or CPs
during Closure Welding for nuclear power reactors
of a VSC-24 Multi-Assembly
Sealed Basket
96-33 Erroneous Data From 05/24/96 All material and fuel cycle
Defective Thermocouple licensees that monitor tem- Results in a Fire perature with thermocouples
96-32 Implementation of 10 CFR 06/05/96 All holders of OLs or CPs
50.55a(g)(6)(ii)(A), for nuclear power reactors
"Augmented Examination
of Reactor Vessel"
96-31 Cross-Tied Safety Injec- 05/22/96 All holders of OLs or CPs
tion Accumulators for pressurized water
reactors
96-30 Inaccuracy of Diagnostic 05/21/96 All holders of OLs or CPs
Equipment for Motor- for nuclear power reactors
Operated Butterfly Valves
96-29 Requirements in 10 CFR 05/20/96 All holders of OLs or CPs
Part 21 for Reporting and for nuclear power reactors
Evaluating Software Errors
96-28 Suggested Guidance Relating 05/01/96 All material and fuel cycle
to Development and Imple- licensees
mentation of Corrective
Action
96-27 Potential Clogging of High 05/01/96 All holders of OLs or CPs
Pressure Safety Injection for pressurized water
Throttle Valves During reactors
Recirculation
96-26 Recent Problems with Over- 04/30/96 All holders of OLs or CPs
head Cranes for nuclear power reactors
96-25 Transversing In-Core Probe 04/30/96 All holders of OLs or CPs
Overwithdrawn at LaSalle for nuclear power reactors
County Station, Unit 1 OL - Operating License
CP - Construction Permit
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
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