Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants: Difference between revisions

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| issue date = 08/21/1987
| issue date = 08/21/1987
| title = Control of Particle Contamination at Nuclear Power Plants
| title = Control of Particle Contamination at Nuclear Power Plants
| author name = Rossi C E
| author name = Rossi C
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 15
| page count = 15
}}
}}
{{#Wiki_filter:..-.i V' 'SINS No.: 6835 iN 87-39 UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:! . . - . i


COMMISSION
V'    'SINS No.:  6835 iN 87-39 UNITED STATES


===OFFICE OF NUCLEAR REACTOR REGULATION===
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555 August 21, 1987 NRC INFORMATION


NOTICE NQ. 87-39: CONTROL OF HOT PARTICLE CONTAMINATION
OFFICE OF NUCLEAR REACTOR REGULATION
 
WASHINGTON, D.C. 20555 August 21, 1987 NRC INFORMATION NOTICE NQ. 87-39:   CONTROL OF HOT PARTICLE CONTAMINATION


AT NUCLEAR POWER PLANTS
AT NUCLEAR POWER PLANTS
Line 27: Line 28:
==Addressees==
==Addressees==
:
:
All nuclear power reactor facilities
                                                                    storage facilities holding


and spent fuel storage facilities
All nuclear power reactor facilities and spent fuel


holding an NRC license or a construction
an NRC license or a construction permit.


permit.Background
Background and
 
and


==Purpose==
==Purpose==
: IE Information
:
 
                                                                    information on events in- IE Information Notice 86-23 (Reference 1) provided skin contamination by small, volving excessive skin exposures resulting from activity (hot particles). Since
Notice 86-23 (Reference
 
1) provided information
 
on events in-volving excessive
 
skin exposures
 
resulting
 
from skin contamination
 
by small, highly radioactive
 
particles
 
with high specific activity (hot particles).
 
Since that information
 
notice was issued, there have been more of these events, and a recent report by the Institute
 
of Nuclear Power Operations (INPO) (Reference
 
2)provides additional
 
information
 
on this subject. This information
 
notice pro-vides information
 
on some of the subsequent
 
events and discusses
 
degraded fuel and a lack of proper radiological
 
control during fuel reconstitution
 
as major sources of hot particles.
 
Generic licensee lessons learned also are included.It is expected that recipients
 
will review this information
 
for applicability
 
to their facilities
 
and consider action, if appropriate, to preclude a similar problem occurring
 
at their facilities.
 
However, suggestions
 
contained
 
in this notice do not constitute
 
NRC requirements;
therefore, no specific action or written response is required.Discussion:
During the first 6 months of 1987, events involving
 
hot particle exposures
 
were reported at nine different
 
nuclear power stations.
 
Two events in late 1986 (at V.C. Summer and San Onofre) involved exposures
 
apparently
 
exceeding
 
NRC regula-tory limits. Attachment
 
1 provides summary descriptions
 
of eight of these events. More detailed descriptions
 
can be obtained from the referenced
 
inspec-tion reports for each event. (Copies of NRC Inspection
 
Reports are available from the NRC Public Document Room, 1717 H Street N.W., Washington, D.C.)Hot particles
 
come primarily
 
from two major sources: degraded fuel and neutron-activated
 
corrosion
 
and wear products (e.g., Stellite).
 
While much of the information
 
in this notice is pertinent
 
to both neutron-activated
 
corrosion and wear product particles (hereafter
 
referred to as activated
 
particles)
and
 
K> QIN 87-39 August 21, 1987 irradiated
 
fuel particles (hereafter
 
referred to as fuel particles), a major concern of this notice is extended facility operation
 
with degraded fuel and the resulting
 
problems with fuel particle contamination.
 
On the basis of an NRC review of licensees'
corrective
 
actions, discussions
 
with licensees'
operating
 
staffs, and information
 
obtained by NRC inspectors, the lessons learned and licensee good practices
 
resulting
 
from the events summarized
 
in Attachment
 
1 are as follows: 1. Extended power plant operation
 
with degraded fuel (leaking fuel pins) can result in widespread
 
dispersal
 
of fuel particles.
 
Some plants continue to experience
 
fuel particle contamination
 
problems long after leaking fuel pins have been removed because of the residual contamination
 
of plant systems. Some plants with these problems have started programs to account for missing fuel pellets and fragments
 
and to identify measures to recover this material.2. Considerations
 
concerning
 
the handling of leaking fuel include the following:
a. Special techniques
 
and precautions
 
for handling leaking fuel bundles are necessary
 
to prevent aggravating
 
the spread of fuel particles.
 
For example, containment
 
devices should be used when reconstituting
 
fuel. The lack of proper radiological
 
controls and oversight
 
of the fuel reconstitution
 
process in the San Onofre 3 fuel pool led to loss of control and dispersal
 
of numerous fuel particles
 
into the pool.Fuel particles
 
then spread through the plant spent fuel systems and to the liquid radwaste systems.b. A damaged, leaking fuel pin that is not properly contained
 
and segregated
 
from the common fuel pool area could be a significant, long-term
 
source of fuel particle contamination.
 
c. Plants should be aware that NSSS vendors' special refueling
 
tools and equipment
 
could be a source of fuel particle contamination.
 
These tools and equipment
 
should be carefully
 
surveyed before they are used and before they are shipped to other facilities.
 
3. Some plants that have operated for extended periods of time with degraded fuel and plants with activated
 
particle problems now have instituted
 
specialized, comprehensive
 
training programs for plant system maintenance
 
workers and general employees.
 
These programs are designed to better inform and prepare the plant staff to cope with the continuing
 
fuel particle problems.
 
Additionally, as part of comprehensive
 
contamination
 
control programs, special new procedures
 
to improve surveys for detection
 
: --..IN 87-39 August 21, 1987 of.hot particles
 
have been prepared and health physics technicians
 
have been trained in their use. Decontamination
 
and dose evaluation
 
methods and procedures
 
that focus on hot particles
 
have been implemented. (See summaries
 
of events at Trojan and.San Onofre in Attachment
 
1.).4.. In general, ;licensees
 
have upgraded their programs for contamination
 
monitoring


of "clean," laundered
highly radioactive particles with high specific been more of these events, and a


anti-contamination
that information notice was issued, there have Operations (INPO) (Reference 2)
            recent report by the Institute of Nuclear Power      This information notice pro- provides additional information on this subject.      and discusses degraded fuel


protective
vides information on some of the subsequent eventsfuel reconstitution as major


clothing (PC). However, PC continues
and a lack of proper radiological control during        learned also are included.


to be a means of transferring
sources of hot particles. Generic licensee lessons


both fuel particles
information for applicability


and activated
It is expected that recipients will review this              to preclude a similar


particles.
to their facilities and consider action,  if appropriate, suggestions contained in this


Some facilities
problem occurring at their facilities. However,            no specific action or


need to consider making their PC monitoring
notice do not constitute NRC requirements; therefore, written response is required.


programs more sensitive.
Discussion:
                                                                      hot particle exposures were


For example, some licensees
During the first 6 months of 1987, events involving Two events in late 1986 (at


that are using contractor
reported at nine different nuclear power stations.            exceeding NRC regula- V.C. Summer and San Onofre) involved exposures apparentlyof eight of these


laundry services found the contrac-tor's alarm on the radiation
tory limits. Attachment 1 provides summary descriptions from the referenced inspec- events. More detailed descriptions can be obtained          Reports are available


monitor (used to screen PC) too high to-detect 0.4 microcurie (VCi) particles.
tion reports for each event. (Copies of NRC Inspection      Washington, D.C.)
              from the NRC Public Document Room, 1717 H Street N.W.,
                                                                          degraded fuel and neutron- Hot particles come primarily from two major sources:          While much of the


Moreover, when commercial
activated corrosion and wear products (e.g., Stellite).                corrosion


laundry services are used, it is possible that PC from a "particle-free" plant* *-can be mixed with PC from a plant with hot particle problems.
information in this notice is pertinent to both neutron-activated


Finally, at.leastrone
as activated  particles)  and


licensee was relying solely on monitoring
and wear product particles (hereafter referred to


of large bundles of washed PC (bulk surveys) and was not monitoring
K>                                QIN                87-39 August 21, 1987 irradiated fuel particles (hereafter referred


samples of individual
to as fuel particles), a major


PC. For plants with identified
concern of this notice is extended facility operation


particle problems, individual
the resulting problems with fuel particle contamination.  with degraded fuel and


PC items may have to be checked before they are reused after cleaning.5. Except for the-Trojan
NRC review of licensees' corrective actions, discussions On the basis of an


event discussed
operating staffs, and information obtained by                with licensees'
                                                  NRC  inspectors,    the lessons


in Attachment
learned and licensee good practices resulting


1, to date, no licensee has reported detecting
from the events summarized in


hot.particles
Attachment 1 are as follows:
1.     Extended power plant operation with degraded fuel


during airborne sampling.However, as a precaution,,some
result in widespread dispersal of fuel particles. (leaking fuel pins) can


licensees
experience fuel particle contamination problems      Some plants continue to


have elected to provide workers with respiratory
pins have been removed because of the residual    long    after leaking fuel


protection
systems. Some plants with these problems have    contamination      of plant


for performing
for missing fuel pellets and fragments and to    started    programs    to account


maintenance
identify measures to recover


on plant systems known to-be a source of hot particles.
this material.


===No plant has reported inhalation===
2.    Considerations concerning the handling of leaking
or ingestion


of hot particles
following:                                            fuel include the


by any worker.6. Hot particles
a.   Special techniques and precautions for handling


in contact with skin.produce
are necessary to prevent aggravating the spread leaking fuel bundles


very high dose rates. Diligent personnel
For example, containment devices should be used of fuel particles.


contamination
fuel. The lack of proper radiological controls when reconstituting


surveys performed
fuel reconstitution process in the San Onofre      and oversight of the


as soon as practical
3  fuel pool led to loss


after .completing
of control and dispersal of numerous fuel particles


work involving
Fuel particles then spread through the plant spent into the pool.


contamination
to the liquid radwaste systems.                        fuel systems and


are needed to minimize potential exposure times.-7. Approximately
b.   A damaged, leaking fuel pin that is not properly


75 percent of the U.S. power reactor facilities
segregated from the common fuel pool area could contained and


are cur-rently using new high-sensitivity
long-term source of fuel particle contamination. be a significant, c.    Plants should be aware that NSSS vendors' special


whole-body
refueling tools and


contamination
equipment could be a source of fuel particle contamination.


monitors.These state-of-the-art
tools and equipment should be carefully surveyed                    These


contamination
and before they are shipped to other facilities.      before  they  are used


monitors increase the probability
3.    Some plants that have operated for extended periods


of detecting
fuel and plants with activated particle problems        of time with degraded


hot-particles
specialized, comprehensive training programs for    now  have instituted


on plant personnel
workers and general employees. These programs        plant   system maintenance


while reducing the likelihood
inform and prepare the plant staff to cope with  are  designed    to better


of inadvertently
particle problems. Additionally, as part of         the  continuing    fuel


releasing
comprehensive


particles
control programs, special new procedures to improve                contamination


from the plant site. To-date, most of-the particles
surveys for detection


found on personnel
: --
                              .          .IN                                87-39 August 21, 1987 of.hot particles have been prepared and health physics technicians      have


have:been
been trained in their use. Decontamination    and  dose  evaluation  methods


detected by these new monitors.
and procedures that focus on hot particles have been implemented. (See


Even with use of the new monitors, a few instances
summaries of events at Trojan and.San Onofre in Attachment 1.)
    .4..  In general, ;licensees have upgraded their programs for contamination


have oc-curred where hot particles
monitoring of "clean," laundered anti-contamination protective clothing


have inadvertently
(PC). However, PC continues to be a means of transferring both fuel


been carried home by workers.and have-been
particles and activated particles. Some facilities need to consider


detected in the home or on the worker returning
making their PC monitoring programs more sensitive. For example,        some


to the site.No significant ,public exposures
licensees that are using contractor  laundry  services  found the  contrac- tor's alarm on the radiation monitor (used to screen PC) too high to


have been reported to date.8. In a recent study for the NRC (Reference
-detect 0.4 microcurie (VCi) particles. Moreover, when commercial plant  laundry


3), it was reported that a plant operating
services are used, it is possible that   PC from  a  "particle-free"
      *    *-can be mixed with PC from a plant with hot particle problems. Finally, at.leastrone licensee was relying solely on monitoring of large bundles


with 0.125 percent pin-hole fuel cladding defects showed a general five-fold
of washed PC (bulk surveys) and was not monitoring samples of individual


increase in whole-body
PC. For plants with identified particle problems, individual PC items


radiation
may have to be checked before they are reused after cleaning.


exposure rates in some
5.    Except for the-Trojan event discussed in Attachment 1, to date, no


IN 87-39 .August 21, 1987 areas of the plant when compared to a sister plant with high-integrity
licensee has reported detecting hot.particles during airborne sampling.


fuel (<0.01percent
However, as a precaution,,some licensees have elected to provide workers


leakers).
with respiratory protection for performing maintenance on plant systems


Around certain plant systems the degraded fuel may elevate.-radiation
known to-be a source of hot particles. No plant has reported inhalation


exposure rates even more. -9. Maintenance-on
or ingestion of hot particles by any worker.


valves with Stellite components
6.  Hot particles in contact with skin.produce very high dose rates. Diligent


can cause introduction
personnel contamination surveys performed as soon as practical after .


of cobalt-containing
completing work involving contamination are needed to minimize potential


debris with Co-60 as the resultant
exposure times.-
      7.    Approximately 75 percent of the U.S. power reactor facilities are cur- rently using new high-sensitivity whole-body contamination monitors.


neutron activation
These state-of-the-art contamination monitors increase the probability of


product. Some plants have instituted
detecting hot-particles on plant personnel while reducing the likelihood


work controls (e.g., use of contain-ment and post-maintenance
of inadvertently releasing particles from the plant site. To-date, most


cleaning)
of-the particles found on personnel have:been detected by these new
to minimize this input into reactor systems (Reference


4).Health Implications
monitors. Even with use of the new monitors, a few instances have oc- curred where hot particles have inadvertently been carried home by workers


and Radiation
. and have-been detected in the home or on the worker returning to the site.


Protection
No significant ,public exposures have been reported to date.


Criteria for Hot Particle-Exposures
8.    In a recent study for the NRC (Reference 3), it was reported that a plant


of Skin: -A hot'particle
operating with 0.125 percent pin-hole fuel cladding defects showed a


on the skin gives a high beta dose to a small area.' Any radia-tion dose to the skin is-assumed
general five-fold increase in whole-body radiation exposure rates in some


to result in'some increased
IN 87-39        .


risk of skin cancer, although'this
August 21, 1987 areas of the plant when compared to a sister plant with


type of cancer is rarely fatal.' Experiments
fuel (<0.01percent leakers). Around certain plant systems    high-integrity


with animals indicate that highly localized
fuel may elevate.-radiation exposure rates even more.              the degraded


irradiation
-
  9.  Maintenance-on valves with Stellite components can cause


of-the skin'by hot particles
cobalt-containing debris with Co-60 as the resultant          introduction of


is less likely to'cause skin cancer than more uniform irradiation
product. Some plants have instituted work controls (e.g.,neutron    activation


by the same quantity of radioactive
ment and post-maintenance cleaning) to minimize this input      use  of contain- systems (Reference 4).                                          into    reactor


material.:-
Health Implications and Radiation Protection Criteria
In addition to any increased


risk of cancer, large doses to the skin from hot particles
for Hot Particle- Exposures of Skin:                  -
  A hot'particle on the skin gives a high beta dose to


also may produce observable
a small area.' Any radia- tion dose to the skin is-assumed to result in'some increased


effects such as reddening, hardening, peeling, or ulceration
cancer, although'this type of cancer is rarely fatal.'            risk of skin


of the skin-immediately
indicate that highly localized irradiation of-the skin'by Experiments      with animals


around the particle;
likely to'cause skin cancer than more uniform irradiation    hot  particles    is less
These effects appear only'after


a-threshold
of radioactive material.:-                                   by  the  same  quantity


dose is exceeded.
In addition to any increased risk of cancer, large


The doses from hot particles
particles also may produce observable effects such doses     to the skin from hot


'equired to-produce
as reddening, hardening, peeling, or ulceration of the skin-immediately around


these effects'in
effects appear only'after a-threshold dose is exceeded.the particle; These


the 'skin are'not known pre-cisely;-Ihowever, -it appears likely, except for a point reddening,-that
particles 'equired to-produce these effects'in the 'skin The doses from hot


these effects will only be seen for doses of hundreds of rems or more.'- No such effects have been seen to date on any workers who have been exposed to-hot particles, even though one exposure has been measured or calculated
cisely;-Ihowever, -it appears likely, except for a point are'not known pre- effects will only be seen for doses of hundreds of rems reddening,-that these


as high as 512 rem.Recent reviews of radiobiology
effects have been seen to date on any workers who have or more.'- No such


and radiation
particles, even though one exposure has been measured been exposed to-hot


protection
512 rem.                                                or calculated as high as


criteria for skin, in-cluding considerations
Recent reviews of radiobiology and radiation protection


of hot particle exposures, have been provided-by-Wells (Reference
cluding considerations of hot particle exposures, have criteria for skin, in- been provided-by-Wells


5) and Charles (References
(Reference 5) and Charles (References 6 and 7). ''
The NRC staff recognizes the need for more'information


6 and 7). ''The NRC staff recognizes
radiation on skin and particularly the effects-of hot on the effects of


the need for more'information
The staff has requested the National Council on Radiation particle irradiation.


on the effects of radiation
Measurements (NCRP) to. study the health significance of       Protection and


on skin and particularly
and to provisde recommendations- based on the findings of  hot  particle exposures


the effects-of
recommendations may result in changes in NRC requirements  this  study. These


hot particle irradiation.
particle exposures. However, until these requirements          with  respect to hot


The staff has requested
are  changed,    IE Infor- mation Notice 86-23 (Reference 1) contains current information


the National Council on Radiation
evaluating doses to skin resulting from hot particles.                for  use  in


Protection
./                    ..                  IN 87-39 August. 21, 1987 Page 5 of S


and Measurements (NCRP) to. study the health significance
oI specific action or.written response is required by this information notice.


of hot particle exposures and to provisde recommendations- based on the findings of this study. These recommendations
* you have any questions about this matter, please contact the Regional


may result in changes in NRC requirements
Admiistrator 'f the appropriate regional office or this office.


with respect to hot particle exposures.
e,
                                            .harles E. Rossi, Director


However, until these requirements
Division of Operational Events Assessment


are changed, IE Infor-mation Notice 86-23 (Reference
1) contains current information
for use in evaluating
doses to skin resulting
from hot particles.
./ ..IN 87-39 August. 21, 1987 Page 5 of S o I specific action or. written response is required by this information
notice.* you have any questions
about this matter, please contact the Regional Admiistrator
'f the appropriate
regional office or this office.e ,.harles E. Rossi, Director Division of Operational
===Events Assessment===
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Technwcal
Technwcal Contact:- James E..Wigginton, NRR


Contact:-
(301) 492-4663 John D. Buchanan, NRR
James E..Wigginton, NRR (301) 492-4663 John D. Buchanan, NRR.(301) 492-7293 References


I. JAE Information
.(301) 492-7293 References


Notice 86-23, "Excessive
I.      JAE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tihn With Hot Particles," April 9, 1986.


Skin Exposures
2i.        nstitute of Nuclear Power Operations, Significant Event Report 18-87 (Rev..2), "Radiation Exposure From Small Particles," July 16, 1987.


Due to Contamina- tihn With Hot Particles," April 9, 1986.2i. nstitute of Nuclear Power Operations, Significant
3,-     Hoeller; M. P., :G. F. Martin, and D. L..Haggard, "The Impact of Fuel


Event Report 18-87 (Rev..2), "Radiation
*-Cladding Failure Events on Occupational Radiation Exposures at Nuclear


Exposure From Small Particles," July 16, 1987.3,- Hoeller; M. P., :G. F. Martin, and D. L..Haggard, "The Impact of Fuel*- Cladding Failure Events on Occupational
:PowerPants. Case Study: PWR During RoutineOperations," NUREG/CR-4485 (PNL-5606), January 1986.


Radiation
Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From


Exposures
H4
          .`Valve IMaintenance," Electric Power Research Institute, EPRI NP-3220, Final


at Nuclear:PowerPants.
::Report, August 1983.      .


Case Study: PWR During RoutineOperations," NUREG/CR-4485 (PNL-5606), January 1986.H4 Heard, D. B., and R. J. Freeman, "Cobalt Contamination
5..    Welli,   3., "Problems Associated With Localized Skin Exposures," in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a


Resulting
:
 
  .         Workshop. heldat Saclay, France, on October 9-11, 1985, Brit.
From.`Valve IMaintenance," Electric Power Research Institute, EPRI NP-3220, Final::Report, August 1983. .5.. Welli, 3., "Problems
 
Associated
 
With Localized
 
Skin Exposures," in "Radia-tion Damage to Skin: Fundamental
 
and Practical
 
Aspects," Proceedings
 
of a: .Workshop.
 
heldat Saclay, France, on October 9-11, 1985, Brit..J3. Radiology, Supplement
 
No. 19, pp. 146-150 (1986).* .6. Charles, 4.W., "The Biological
 
Bases of Radiation
 
Protection


Criteria for Superficial, Low Penetrating
.J3.  Radiology, Supplement No. 19, pp. 146-150 (1986).


Radiation
* .6.        Charles, 4.W., "The Biological Bases of Radiation Protection Criteria for


Exposure," in "Dosimetry
Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta


of Beta Particles
Particles and Low Energy X-Rays," Proceedings of a Workshop held at


and Low Energy X-Rays," Proceedings
Sacay, Francei October 7-9,-1985," Radiation Protection Dosimetry 14 (No.


of a Workshop held at-Sacay, Francei October 7-9,-1985," Radiation
-
                      79-90 (1986).


Protection
P2),pp.


Dosimetry
-7. Charles, 14. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent


14 (No.P2),pp. 79-90 (1986).-7. Charles, 14. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent..Advances
. .Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).


in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).Attachments;..
Attachments;.. ..


..-*. l. EventSummaries
-l.*. EventSummaries


.2.. List-4f Recently Issued NRC Information
.2.. List-4f Recently Issued NRC Information Notices


Notices
Attachment 1 IN 87-39 August 21, 1987 EVENT SUMMARIES


Attachment
San Onofre 3. Events Durina November 1986  - March 1987, Inspection Report


1 IN 87-39 August 21, 1987 EVENT SUMMARIES San Onofre 3. Events Durina November 1986 -March 1987, Inspection
No. 50-362/86-37 Background:
At the onset of the first fuel cycle, significant fuel degradation was evident.


Report No. 50-362/86-37 Background:
The plant continued to operate with approximately 105 defective fuel pins. In
At the onset of the first fuel cycle, significant


fuel degradation
late 1985 during the first refueling outage, a fuel pin was inadvertently


was evident.The plant continued
pulled apart during the fuel reconstitution process. Several fuel pellets fell


to operate with approximately
and dispersed throughout the fuel pool. Fuel particles had previously been


105 defective
detected early on during reconstitution on fuel handling tools and on the


fuel pins. In late 1985 during the first refueling
refueling floors. All the severely damaged fuel pins were then grouped into


outage, a fuel pin was inadvertently
one fuel bundle and stored in the pool without any containment.
 
pulled apart during the fuel reconstitution
 
process. Several fuel pellets fell and dispersed
 
throughout
 
the fuel pool. Fuel particles
 
had previously
 
been detected early on during reconstitution
 
on fuel handling tools and on the refueling
 
floors. All the severely damaged fuel pins were then grouped into one fuel bundle and stored in the pool without any containment.


Event Specifics:
Event Specifics:
From January 2 through February 20, 1987, the licensee's
From January 2 through February 20, 1987, the licensee's aggressive hot parti- cle inventory and tracking system indicated that 92 "new" fuel particles
 
aggressive
 
hot parti-cle inventory
 
and tracking system indicated


that 92 "new" fuel particles (recently
(recently neutron irradiated), 155 "old" fuel particles, 51 ruthenium, 84 crud, and 42 cobalt particles had been found and analyzed. Before 1987, no formal


neutron irradiated), 155 "old" fuel particles, 51 ruthenium, 84 crud, and 42 cobalt particles
tracking program existed.


had been found and analyzed.
Several incidents involving hot particles have occurred, including an apparent


Before 1987, no formal tracking program existed.Several incidents
worker extremity exposure (hand) of 512 rem during November 1986. As a result, appropriate NRC enforcement actions are currently underway. Three events


involving
involving the inadvertent release of hot particles from the plant site occurred


hot particles
in February 1987. In two of these events, the radiation dose to the public was


have occurred, including
determined to be negligible. However, the third event involved a 0.2.;Ci


an apparent worker extremity
particle found by a worker at his home during a self-initiated radiological


exposure (hand) of 512 rem during November 1986. As a result, appropriate
survey. The licensee has not yet estimated the potential dose to the worker's


NRC enforcement
family as a result of this occurrence.


actions are currently
In the licensee's licensee event report (LER No. 86-015, Revision 1) of Febru- ary 22, 1987, the following program improvements for detecting hot particles


underway.
and controlling personnel exposures from hot particles were described:
                                                    f


Three events involving
Extensive, mandatory use of exceedingly sensitive fixed instrumentation


the inadvertent
(frisking booths) for the detection of personnel contamination;
      Special training (including hands-on laboratory exercises) in radioactive


release of hot particles
particle characteristics and survey techniques for all Health Physics


from the plant site occurred in February 1987. In two of these events, the radiation
Technicians;
        C-.


dose to the public was determined
Attachment 1 IN 87-39 August 21, 1987 Oral and written indoctrination of all managers, first line super- visors and workers in the special problems associated with radio- active particles, including the methods each person must employ to


to be negligible.
protect himself;
        Special procedures to assure detection and control of radioactive


However, the third event involved a 0.2.;Ci particle found by a worker at his home during a self-initiated
particles which feature the establishment of a clearly identifiable


radiological
zone, to demark and contain such particles, surrounded by clearly


survey. The licensee has not yet estimated
identified buffer zones (or solid physical barriers) which are


the potential
surveyed frequently to verify that control is being maintained;
        Maintenance and wide publication of a radioactive particle census


dose to the worker's family as a result of this occurrence.
during outages to maintain station awareness;
        The establishment of a Task Force to recommend and implement action to


In the licensee's
minimize the future production and movement of radioactive particles.


licensee event report (LER No. 86-015, Revision 1) of Febru-ary 22, 1987, the following
Trojan, April, 1987, Inspection Report No. 50-344/87-15 Background:
  The facility has operated since July 1982 with an estimated 112 fuel pellets


program improvements
unaccounted for throughout the reactor and support plant systems. The licensee


for detecting
recovered or located about 264 pellets of the estimated 376 missing after the


hot particles and controlling
1982 refueling outage, which occurred because of the baffle jetting problems of


personnel
the 1981 fuel cycle. (See IE Information Notice 82-27, "Fuel Rod Degradation


exposures
Resulting From Baffle.Water-Jet Impingement," August .5, 1982.)
  Event Specifics:
  Shortly after the start of the 1987 refueling outage in April, a significant


from hot particles
increase in personnel skin contaminations occurred. On April 9, high surface


were described:
contamination (up to 300,000 dpm/100 cm2) and high airborne activity levels
f Extensive, mandatory


use of exceedingly
-.(2E-7 pCi/cc, mixed fission products) in containment resulted from the dis- persal of fuel fragments during reactor vessel. stud removal and stud-hole


sensitive
plugging operations. The workers in the reactor cavity were wearing respira- tors and no excessive uptakes of.radioactive materials were detected during


fixed instrumentation (frisking
followup whole-body counting. Because of the spread of contamination to the


booths) for the detection
spent fuel building, the licensee stopped all- reactor building cavity work and


of personnel
all personnel evacuated the area that afternoon.


contamination;
On April 10, a licensee radiation survey located a hot spot on the cavity floor
Special training (including


hands-on laboratory
near a reactor vessel stud-hole (>100 rad/hr beta and 30 R/hr gamma contact


exercises)  
reading using a portable ion-chamber survey.instrument). On April 11, another
in radioactive


particle characteristics
worker located what appeared to be about one-half of a fuel pellet in the


and survey techniques
flange area at the stud hole. This partial fuel pellet was removed on


for all Health Physics Technicians;
April 12.
C-.


Attachment
Attachment 1 IN 87-39 August 21, 1987 On April 17, a radiation protection technician, after performing a survey of


1 IN 87-39 August 21, 1987 Oral and written indoctrination
the lower refueling cavity, discovered a fuel particle lodged in his protective


of all managers, first line super-visors and workers in the special problems associated
rubber shoe cover. This particle was later determined to be composed of


with radio-active particles, including
approximately 50 mCi of mixed fission product activity; showed readings of 1200
mR/hr with the window open and 250 mR/hr with the window closed. After a


the methods each person must employ to protect himself;Special procedures
careful time-and-motion study of the technician's activities, the licensee


to assure detection
determined that no NRC regulatory dose limits were exceeded. (Licensee esti- mates were 1.2 rem to whole body; 4.6 rem to skin; 9.6 rem to extremities.)
In general, it appears that the licensee experienced a programmatic breakdown


and control of radioactive
that resulted in several workers receiving significant, unnecessary radiation


particles
exposures from fuel particle contamination. In LER No. 87-08'dated May 8, 1987, the licensee identified the following additional concerns and'corrective


which feature the establishment
actions. The LER stated in part:
    Workers entering containment on April 9 were not-aware of the fuel


of a clearly identifiable
particle hazards. As a corrective measure, all personnel with


zone, to demark and contain such particles, surrounded
access to radiological control areas were retrained to be informed of


by clearly identified
the fuel particle problem and perform hands-on training to demonstrate


buffer zones (or solid physical barriers)
competence in anti-contamination clothing use. Daily reports
which are surveyed frequently


to verify that control is being maintained;
are being provided to workers on the status of containment activities.
Maintenance


and wide publication
Radiation surveys and record keeping were inadequate. As a corrective


of a radioactive
measure, new procedures were developed to specifically address


particle census during outages to maintain station awareness;
discrete radioactive particles. All radiation protection technicians
The establishment
 
of a Task Force to recommend
 
and implement
 
action to minimize the future production
 
and movement of radioactive
 
particles.
 
Trojan, April, 1987, Inspection
 
Report No. 50-344/87-15 Background:
The facility has operated since July 1982 with an estimated
 
112 fuel pellets unaccounted
 
for throughout
 
the reactor and support plant systems. The licensee recovered
 
or located about 264 pellets of the estimated
 
376 missing after the 1982 refueling
 
outage, which occurred because of the baffle jetting problems of the 1981 fuel cycle. (See IE Information
 
Notice 82-27, "Fuel Rod Degradation
 
Resulting
 
From Baffle.Water-Jet
 
Impingement," August .5, 1982.)Event Specifics:
Shortly after the start of the 1987 refueling
 
outage in April, a significant
 
increase in personnel
 
skin contaminations
 
occurred.
 
On April 9, high surface contamination (up to 300,000 dpm/100 cm 2) and high airborne activity levels-.(2E-7 pCi/cc, mixed fission products)
in containment
 
resulted from the dis-persal of fuel fragments
 
during reactor vessel. stud removal and stud-hole plugging operations.
 
The workers in the reactor cavity were wearing respira-tors and no excessive
 
uptakes of.radioactive
 
materials
 
were detected during followup whole-body
 
counting.
 
Because of the spread of contamination
 
to the spent fuel building, the licensee stopped all- reactor building cavity work and all personnel
 
evacuated
 
the area that afternoon.
 
On April 10, a licensee radiation
 
survey located a hot spot on the cavity floor near a reactor vessel stud-hole
 
(>100 rad/hr beta and 30 R/hr gamma contact reading using a portable ion-chamber
 
survey.instrument).
 
On April 11, another worker located what appeared to be about one-half of a fuel pellet in the flange area at the stud hole. This partial fuel pellet was removed on April 12.
 
Attachment
 
1 IN 87-39 August 21, 1987 On April 17, a radiation
 
protection
 
technician, after performing
 
a survey of the lower refueling
 
cavity, discovered
 
a fuel particle lodged in his protective
 
rubber shoe cover. This particle was later determined
 
to be composed of approximately
 
50 mCi of mixed fission product activity;
showed readings of 1200 mR/hr with the window open and 250 mR/hr with the window closed. After a careful time-and-motion
 
study of the technician's
 
activities, the licensee determined
 
that no NRC regulatory
 
dose limits were exceeded. (Licensee
 
esti-mates were 1.2 rem to whole body; 4.6 rem to skin; 9.6 rem to extremities.)
In general, it appears that the licensee experienced
 
a programmatic
 
breakdown that resulted in several workers receiving
 
significant, unnecessary
 
radiation exposures
 
from fuel particle contamination.
 
In LER No. 87-08'dated
 
May 8, 1987, the licensee identified
 
the following
 
additional
 
concerns and'corrective
 
actions. The LER stated in part: Workers entering containment
 
on April 9 were not-aware
 
of the fuel particle hazards. As a corrective
 
measure, all personnel
 
with access to radiological
 
control areas were retrained
 
to be informed of the fuel particle problem and perform hands-on training to demonstrate
 
competence
 
in anti-contamination
 
clothing use. Daily reports are being provided to workers on the status of containment
 
activities.
 
Radiation
 
surveys and record keeping were inadequate.
 
===As a corrective===
measure, new procedures
 
were developed
 
to specifically
 
address discrete radioactive
 
particles.
 
All radiation
 
protection
 
technicians


have been trained on these new procedures...
have been trained on these new procedures...


There was-insufficient
There was-insufficient extremity monitoring and no procedures for
 
extremity
 
monitoring
 
and no procedures


for particle control. As a corrective
particle control. As a corrective measure, procedures have been


measure, procedures
prepared to address particle control. Additional extremity moni- toring is being utilized.


have been prepared to address particle control. Additional
Evaluation of radiological events needs to be improved. A'new-pro''
      cedure will be prepared for documenting and evaluating radiologicalj :
      events.-
      Review of radiation protection activities.'is insufficient. A new


extremity
separate onsite review committee will be established to evaluate


moni-toring is being utilized.Evaluation
radiological events and to routinely review the performance of the


of radiological
Radiation Protection Department.  -
      Insufficient staffing existed. Increasing the manpower in both the


events needs to be improved.
onsite Radiation Protection Department and the corporate Radiological


A'new-pro''
Safety Branch of the Nuclear Safety and Regulation Department is being
cedure will be prepared for documenting


and evaluating
pursued.


radiologicalj
Attachment 1 IN 87-39 August 21, 1987 Problems existed due to insufficient radiation monitoring and surveying


: events.-Review of radiation
equipment. Additional equipment including new portal monitors and


protection
radiation monitoring equipment has been procured.


activities.'is
There was the potential for radiation exposure to individuals from fuel


insufficient.
particles on anti-contamination clothing. An evaluation for potential


A new separate onsite review committee
exposure is in progress.


will be established
V. C. Summer, November 1986, Inspection Report No. 50-395/86-22 After working-in a "clean" area where no protective clothing was required, contamination was detected on the hand of an electrician who had worked on a


to evaluate radiological
control panel for the overhead crane in the fuel handling building. After


events and to routinely
measuring the dose rates (window open and window closed) with a portable survey


review the performance
instrument the worker's hand was decontaminated. The contaminant was not


of the Radiation
retained for further analysis. Based on the survey instrument readings, the


Protection
dose to the workers hand was calculated to be about 420 rems (at a depth of


Department.
7  mg/cm 2                              2 averaged over an area of 1 cm ).


-Insufficient
Salem Unit 2, April 1987, Inspection Report No. 50-311/87-11 A fuel particle was detected by a whole-body contamination monitor on a work- er's arm. The particle was identified as a fuel particle (about 225 days since


staffing existed. Increasing
in core) by using a gamma-ray spectrometer [Ge(Li) detector]. The licensee


the manpower in both the onsite Radiation
believes that the source of the particle was from the last refueling outage


Protection
about 8 months earlier.


Department
Yankee Nuclear Power Station, May 1987, Inspection Report No. 50-29/87-10
A potential skin exposure of 7.6 rem to a worker's scalp occurred from an


and the corporate
activated particle. The apparent source of the particle was the worker's PC


===Radiological===
hood. After its discovery, the particle remained on the worker's scalp for
Safety Branch of the Nuclear Safety and Regulation


Department
about 78 hours, awaiting medical assistance to remove the particle. Prior to


is being pursued.
medical assistance arriving on site, the particle was removed by shaving the


Attachment
hair. Earlier in May, the licensee reported that, during fuel assembly move- ment, pieces of fuel rods were seen to have fallen away from the assembly and


1 IN 87-39 August 21, 1987 Problems existed due to insufficient
land on top of the reactor core and in the refueling cavity area. Fuel recon- stitution was in progress. -


radiation
Attachment 1 IN 87-39 August 21, 1987 Indian Point Unit 3, May 1987, Inspection Report No. 50-286/87-18 A maintenance foreman exiting the containment after helping to replace steam


monitoring
generator manway covers received an estimated 4 rem dose to the skin (in back


and surveying equipment.
of neck) from an activated zirconium particle. It appears the particle dis- lodged from his PC hood and fell on his neck during temporary removal of the


Additional
hood during a work rest-break.


equipment
Quad Cities/Dresden/Zion, 1986 and 1987 A special program to investigate hot particle incidents has been in place at


including
these Commonwealth Edison Company facilities for the last 1-2 years. A total


new portal monitors and radiation
of approximately 100 individual hot particles were found on workers' skin or


monitoring
clothing in 1986. Approximately 130 particles were found in the first six


equipment
months of 1987. The particles have been predominantly Co-60 with activities


has been procured.There was the potential
ranging from about 0.01 to 1 pCi. Those particles were analyzed for physical


for radiation
size; the smallest was 20 microns. The licensee investigated each event and


exposure to individuals
calculated skin doses. No overexposures have been reported. The transfer


from fuel particles
mechanism of the particles to the workers has not been positively identified.


on anti-contamination
Callaway Station, 1986 Period, Report No. 50-483/8700 (DRSS)
The licensee experienced ten hot particle skin contamination incidents primari- ly during the refueling outage early during the year. No NRC dose limits were


clothing.
exceeded. Ineffective frisking (hand-held pancake GM-tube) of laundered PC and


An evaluation
potentially degraded dry-cleaning fluid quality (leading to cross-contami- nation of PC during cleaning) were identified by the licensee as possible


for potential exposure is in progress.V. C. Summer, November 1986, Inspection
contributors to this contamination problem.


Report No. 50-395/86-22 After working-in
Attachment 2 IN 87-39 August 21, 1987 LIST OF RECENTLY ISSUED


a "clean" area where no protective
INFORMATION NOTICES 1987


clothing was required, contamination
===Information                                  Date of===
Notice No.    Subject                      Issuance Issued to


was detected on the hand of an electrician
87-38          Inadequate or Inadvertent    8/17/87  All nuclear power


who had worked on a control panel for the overhead crane in the fuel handling building.
Blocking of Valve Movement            reactor facilities


After measuring
holding an OL or CP.


the dose rates (window open and window closed) with a portable survey instrument
87-37          Compliance with the General  8/10/87  All persons specifi- License Provisions of                  cally licensed to


the worker's hand was decontaminated.
10 CFR Part 31                        manufacture or to


The contaminant
initially transfer


was not retained for further analysis.
devices containing


Based on the survey instrument
radioactive material


readings, the dose to the workers hand was calculated
to general licensees, as defined in 10 CFR


to be about 420 rems (at a depth of 7 mg/cm 2 averaged over an area of 1 cm 2).Salem Unit 2, April 1987, Inspection
Part 31.


Report No. 50-311/87-11 A fuel particle was detected by a whole-body
87-36          Significant Unexpected        8/4/87   All nuclear power


contamination
Erosion of Feedwater Lines            reactor facilities


monitor on a work-er's arm. The particle was identified
holding an OL or CP.


as a fuel particle (about 225 days since in core) by using a gamma-ray
87-35          Reactor Trip Breaker,        7/30/87  All nuclear power


spectrometer
Westinghouse Model DS-416,            reactor facilities


[Ge(Li) detector].
Failed to Open on Manual              holding an OL or


The licensee believes that the source of the particle was from the last refueling
Initiation from the Control            CP employing W DS-416 Room                                  reactor trip breakers.


outage about 8 months earlier.Yankee Nuclear Power Station, May 1987, Inspection
87-34          Single Failures in Auxiliary  7/24/87  All holders of an


Report No. 50-29/87-10
Feedwater Systems                      OL or a CP for
A potential


skin exposure of 7.6 rem to a worker's scalp occurred from an activated
pressurized water


particle.
reactor facilities.


The apparent source of the particle was the worker's PC hood. After its discovery, the particle remained on the worker's scalp for about 78 hours, awaiting medical assistance
87-33          Applicability of 10 CFR      7/24/87  All NRC licensees.


to remove the particle.
Part 21 to Nonlicensees


Prior to medical assistance
87-32          Deficiencies in the Testing  7/10/87  All nuclear power


arriving on site, the particle was removed by shaving the hair. Earlier in May, the licensee reported that, during fuel assembly move-ment, pieces of fuel rods were seen to have fallen away from the assembly and land on top of the reactor core and in the refueling
of Nuclear-Grade Activated            reactor facilities


cavity area. Fuel recon-stitution
Charcoal.                              holding an OL or CP.


was in progress.
87-31          Blocking, Bracing, and        7/10/87  All NRC licensees.


-
Securing of Radioactive
Attachment


1 IN 87-39 August 21, 1987 Indian Point Unit 3, May 1987, Inspection
Materials Packages in


Report No. 50-286/87-18 A maintenance
Transportation.


foreman exiting the containment
. :
OL = Operating License


after helping to replace steam generator
CP = Construction Permit


manway covers received an estimated
- .V    IN 87-XX


4 rem dose to the skin (in back of neck) from an activated
August, 1987 No specific action or written response is required by this information notice.


zirconium
If you have any questions about this matter, please contact the Regional


particle.
Administrator of the appropriate regional office or this office.


It appears the particle dis-lodged from his PC hood and fell on his neck during temporary
Charles E. Rossi, Director


removal of the hood during a work rest-break.
Division of Operational Events Assessment


Quad Cities/Dresden/Zion, 1986 and 1987 A special program to investigate
hot particle incidents
has been in place at these Commonwealth
Edison Company facilities
for the last 1-2 years. A total of approximately
100 individual
hot particles
were found on workers' skin or clothing in 1986. Approximately
130 particles
were found in the first six months of 1987. The particles
have been predominantly
Co-60 with activities
ranging from about 0.01 to 1 pCi. Those particles
were analyzed for physical size; the smallest was 20 microns. The licensee investigated
each event and calculated
skin doses. No overexposures
have been reported.
The transfer mechanism
of the particles
to the workers has not been positively
identified.
Callaway Station, 1986 Period, Report No. 50-483/8700 (DRSS)The licensee experienced
ten hot particle skin contamination
incidents
primari-ly during the refueling
outage early during the year. No NRC dose limits were exceeded.
Ineffective
frisking (hand-held
pancake GM-tube) of laundered
PC and potentially
degraded dry-cleaning
fluid quality (leading to cross-contami- nation of PC during cleaning)
were identified
by the licensee as possible contributors
to this contamination
problem.
Attachment
2 IN 87-39 August 21, 1987 LIST OF RECENTLY ISSUED INFORMATION
NOTICES 1987 Information
Date of Notice No. Subject Issuance Issued to 87-38 87-37 87-36 87-35 87-34 87-33 87-32 Inadequate
or Inadvertent
Blocking of Valve Movement Compliance
with the General License Provisions
of 10 CFR Part 31 Significant
Unexpected
Erosion of Feedwater
Lines Reactor Trip Breaker, Westinghouse
Model DS-416, Failed to Open on Manual Initiation
from the Control Room Single Failures in Auxiliary Feedwater
Systems Applicability
of 10 CFR Part 21 to Nonlicensees
Deficiencies
in the Testing of Nuclear-Grade
Activated Charcoal.8/17/87 8/10/87 8/4/87 7/30/87 7/24/87 7/24/87 7/10/87 7/10/87 All nuclear power reactor facilities
holding an OL or CP.All persons specifi-cally licensed to manufacture
or to initially
transfer devices containing
radioactive
material to general licensees, as defined in 10 CFR Part 31.All nuclear power reactor facilities
holding an OL or CP.All nuclear power reactor facilities
holding an OL or CP employing
W DS-416 reactor trip breakers.All holders of an OL or a CP for pressurized
water reactor facilities.
All NRC licensees.
===All nuclear power reactor facilities===
holding an OL or CP.All NRC licensees.
87-31 Blocking, Bracing, and Securing of Radioactive
Materials
Packages in Transportation.
.: OL =CP =Operating
License Construction
Permit
-.V IN 87-XX August, 1987 No specific action or written response is required by this information
notice.If you have any questions
about this matter, please contact the Regional Administrator
of the appropriate
regional office or this office.Charles E. Rossi, Director Division of Operational
===Events Assessment===
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Technical
===Technical Contact:===


Contact: James E. Wigginton, NRR (301) 492-4663 John 0. Buchanan, NRR (301) 492-7293 References
===James E. Wigginton, NRR===
                    (301) 492-4663 John 0. Buchanan, NRR


1. IE Information
(301) 492-7293 References


Notice 86-23, "Excessive
1.  IE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tion With Hot Particles," April 9, 1986.


Skin Exposures
2.  Institute of Nuclear Power Operations, Significant Event Report 18-87 (Rev. 2), "Radiation Exposure From Small Particles," July 16, 1987.


Due to Contamina- tion With Hot Particles," April 9, 1986.2. Institute
3.  Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel


of Nuclear Power Operations, Significant
Cladding Failure Events on Occupational Radiation Exposures at Nuclear


Event Report 18-87 (Rev. 2), "Radiation
Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.


Exposure From Small Particles," July 16, 1987.3. Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel Cladding Failure Events on Occupational
4.   Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From


Radiation
Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final


Exposures
Report, August 1983.


at Nuclear Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.4. Heard, D. B., and R. J. Freeman, "Cobalt Contamination
5.   Wells, J., "Problems Associated With Localized Skin Exposures," in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a


Resulting
Workshop held at Saclay, France, on October 9-11, 1985, Brit.


From Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final Report, August 1983.5. Wells, J., "Problems
J. Radiology, Supplement No. 19, pp. 146-150 (1986).


Associated
6.  Charles, M. W,., "The Biological Bases of Radiation Protection Criteria for


With Localized
Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta


Skin Exposures," in "Radia-tion Damage to Skin: Fundamental
Particles and Low Energy X-Rays," Proceedings of a Workshop held at


and Practical
Saclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.


Aspects," Proceedings
2), pp. 79-90 (1986).


of a Workshop held at Saclay, France, on October 9-11, 1985, Brit.J. Radiology, Supplement
7.  Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent


No. 19, pp. 146-150 (1986).6. Charles, M. W,., "The Biological
Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).


Bases of Radiation
Attachments:
1. Events Summaries


Protection
2. List of Recently Issued NRC Information Notices


Criteria for Superficial, Low Penetrating
*SEE PREVIOUS CONCURRENCES                        p          g  C


Radiation
/OGCB:DOEA:NRR
 
Exposure," in "Dosimetry
 
of Beta Particles
 
and Low Energy X-Rays," Proceedings
 
of a Workshop held at Saclay, France, October 7-9, 1985," Radiation
 
Protection
 
Dosimetry
 
14 (No.2), pp. 79-90 (1986).7. Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).Attachments:
1. Events Summaries 2. List of Recently Issued NRC Information
 
Notices*SEE PREVIOUS CONCURRENCES
 
C p g /OGCB:DOEA:NRR


z UERidlHBerlinger
z UERidlHBerlinger


RBDE-R R PN n 1 847 4 S8//' 87 8/ /87 RPB:DREP:NRR
RBDE-R
 
*RP:DREP:NRR


R P:NR '*D:DREP:NRR
PN R   n      1 847    4  S8//' 87      8/ /87 RPB:DREP:NRR  *RP:DREP:NRR          R  P:NR   '*D:DREP:NRR   *PPMB:ARM


*PPMB:ARM JEWigginton
JEWigginton   JDBuchanan      LJCunningham        FJCongel      TechEd


JDBuchanan
7/28/87        7/28/87        7/28/87            7/28/87        7/28/87


LJCunningham
IN 87-XX


FJCongel TechEd 7/28/87 7/28/87 7/28/87 7/28/87 7/28/87 IN 87-XX August, 1987 No specific action or written response is required by this information
August, 1987 No specific action or written response is required by this information notice.


notice.If you have any questions
If you have any questions about this matter, please contact the Regional


about this matter, please contact the Regional Administrator
Administrator of the appropriate regional office or this office.


of the appropriate
Charles E. Rossi, Director


regional office or this office.Charles E. Rossi, Director Division of Operational
Division of Operational Events Assessment


===Events Assessment===
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Technical
===Technical Contact:===
 
Contact: James E. Wigginton, NRR (301) 492-4663 John D. Buchanan, NRR (301) 492-7293 References


1. "IE Information
===James E. Wigginton, NRR===
                      (301) 492-4663 John D. Buchanan, NRR


Notice 86-23, "Excessive
(301) 492-7293 References


Skin Exposures
1.    "IE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tion With Hot Particles," April 9, 1986.


Due to Contamina- tion With Hot Particles," April 9, 1986.2. Institute
2.    Institute of Nuclear Power Operations, Significant Event Report 18-87 (Rev. 2), "Radiation Exposure From Small Particles," July 16, 1987.


of Nuclear Power Operations, Significant
3.    Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel


Event Report 18-87 (Rev. 2), "Radiation
Cladding Failure Events on Occupational Radiation Exposures at Nuclear


Exposure From Small Particles," July 16, 1987.3. Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel Cladding Failure Events on Occupational
Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.


Radiation
4.    Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From


Exposures
Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final


at Nuclear Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.4. Heard, D. B., and R. J. Freeman, "Cobalt Contamination
Report, August 1983.


Resulting
5.    Wells, J., "Problems Associated With Localized Skin Exposures," in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a


From Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final Report, August 1983.5. Wells, J., "Problems
Workshop held at Saclay, France, on October 9-11, 1985, Brit.


Associated
J. Radiology, Supplement No. 19, pp. 146-150 (1986).


With Localized
6.    Charles, M. W., "The Biological Bases of Radiation Protection Criteria for


Skin Exposures," in "Radia-tion Damage to Skin: Fundamental
Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta


and Practical
Particles and Low Energy X-Rays," Proceedings of a Workshop held at


Aspects," Proceedings
Saclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.


of a Workshop held at Saclay, France, on October 9-11, 1985, Brit.J. Radiology, Supplement
2), pp. 79-90 (1986).


No. 19, pp. 146-150 (1986).6. Charles, M. W., "The Biological
7.   Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and


Bases of Radiation
Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.


Protection
69-81 (1986).


Criteria for Superficial, Low Penetrating
Attachments:
1. Events Summaries


Radiation
2. List of Recently Issued


Exposure," in "Dosimetry
NRC Information Notices


of Beta Particles
*SEE PREVIOUS CONCURRENCES                          D/DOEA:NRR    C/OGCB:DOEA:NRR


and Low Energy X-Rays," Proceedings
CERossi        CHBerlinger


of a Workshop held at Saclay, France, October 7-9, 1985," Radiation
8/ /87        8/10/87
*RPB:DREP:NRR  *RPB:DREP:NRR  *AC:RPB:DREP:NRR    *D:DREP:NRR    *PPMB:ARM


Protection
JEWigginton    JDBuchanan      LJCunningham        FJCongel      TechEd


Dosimetry
7/28/87        7/28/87        7/28/87            7/28/87        7/28/87


14 (No.2), pp. 79-90 (1986).7. Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.69-81 (1986).Attachments:
~'V                                          IN 87-XX
1. Events Summaries 2. List of Recently Issued NRC Information


Notices*SEE PREVIOUS CONCURRENCES
August, 1987 No specific action or written response is required by this information notice.


D/DOEA:NRR
If you have any questions about this matter, please contact the Regional


C/OGCB:DOEA:NRR
Administrator of the appropriate regional office or this office.


===CERossi CHBerlinger===
Charles E. Rossi, Director
8/ /87 8/10/87*RPB:DREP:NRR


*RPB:DREP:NRR
Division of Operational Events Assessment


*AC:RPB:DREP:NRR
*D:DREP:NRR
*PPMB:ARM JEWigginton
JDBuchanan
LJCunningham
FJCongel TechEd 7/28/87 7/28/87 7/28/87 7/28/87 7/28/87
~' V IN 87-XX August, 1987 No specific action or written response is required by this information
notice.If you have any questions
about this matter, please contact the Regional Administrator
of the appropriate
regional office or this office.Charles E. Rossi, Director Division of Operational
===Events Assessment===
Office of Nuclear Reactor Regulation
Office of Nuclear Reactor Regulation


Technical
===Technical Contact:===
 
Contact: James E. Wigginton, NRR (301) 492-4663 John D. Buchanan, NRR (301) 492-7293 References
 
1. "IE Information
 
Notice 86-23, "Excessive
 
Skin Exposures
 
Due to Contamina- tion With Hot Particles," April 9, 1986.2. Institute
 
of Nuclear Power Operations, Significant
 
Event Report 18-87 (Rev. 2), "Radiation


Exposure From Small Particles," July 16, 1987.3. Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel Cladding Failure Events on Occupational
===James E. Wigginton, NRR===
                      (301) 492-4663 John D. Buchanan, NRR


Radiation
(301) 492-7293 References


Exposures
1.    "IE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tion With Hot Particles," April 9, 1986.


at Nuclear Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.4. Heard, D. B., and R. J. Freeman, "Cobalt Contamination
2.    Institute of Nuclear Power Operations, Significant Event Report 18-87 (Rev. 2), "Radiation Exposure From Small Particles," July 16, 1987.


Resulting
3.    Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel


From Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final Report, August 1983.5. Wells, J., "Problems
Cladding Failure Events on Occupational Radiation Exposures at Nuclear


Associated
Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.


With Localized
4.    Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From


Skin Exposures,'
Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final
in "Radia-tion Damage to Skin: Fundamental


and Practical
Report, August 1983.


Aspects," Proceedings
5.    Wells, J., "Problems Associated With Localized Skin Exposures,' in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a


of a Workshop held at Saclay, France, on October 9-11, 1985, Brit.J. Radiology, Supplement
Workshop held at Saclay, France, on October 9-11, 1985, Brit.


No. 19, pp. 146-150 (1986).6. Charles, M. W., "The Biological
J. Radiology, Supplement No. 19, pp. 146-150 (1986).


Bases of Radiation
6.    Charles, M. W., "The Biological Bases of Radiation Protection Criteria for


Protection
Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta


Criteria for Superficial, Low Penetrating
Particles and Low Energy X-Rays," Proceedings of a Workshop held at


Radiation
Saclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.


Exposure," in "Dosimetry
2), pp. 79-90 (1986).


of Beta Particles
7.    Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and


and Low Energy X-Rays," Proceedings
Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.


of a Workshop held at Saclay, France, October 7-9, 1985," Radiation
69-81 (1986).


Protection
Attachments:
1. Events Summaries


Dosimetry
2. List of Recently Issued


14 (No.2), pp. 79-90 (1986).7. Charles, M. W., Recent Advances 69-81 (1986)."Skin, Eye, and Testis: Current Exposure Problems and in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.Attachments:
NRC Information Notices
1. Events Summaries 2. List of Recently Issued NRC Information


Notices C/OGCB:DOEA:NRF
C/OGCB:DOEA:NRF


CHBerlinger
CHBerlinger


R i EP:NRR J Eigginton 7/&X/87 RPM :NRR J. an 7/ig/87 A REP:NRR LJC I4nningham
R i EP:NRR       RPM       :NRR     A   REP:NRR     D:DREP:NRRI


7}(%/87 D:DREP:NRRI
JEigginton      J.      an    LJC I4nningham        FJCongel      Techd


FJCongel-4/ti/8 7 Techd 7/w}}
7/&X/87          7/ig/87        7}(%/87              -4/ti/8 7       7/w}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Latest revision as of 04:00, 24 November 2019

Control of Particle Contamination at Nuclear Power Plants
ML031130618
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill
Issue date: 08/21/1987
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-87-039, NUDOCS 8708170408
Download: ML031130618 (15)


! . . - . i

V' 'SINS No.: 6835 iN 87-39 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555 August 21, 1987 NRC INFORMATION NOTICE NQ. 87-39: CONTROL OF HOT PARTICLE CONTAMINATION

AT NUCLEAR POWER PLANTS

Addressees

storage facilities holding

All nuclear power reactor facilities and spent fuel

an NRC license or a construction permit.

Background and

Purpose

information on events in- IE Information Notice 86-23 (Reference 1) provided skin contamination by small, volving excessive skin exposures resulting from activity (hot particles). Since

highly radioactive particles with high specific been more of these events, and a

that information notice was issued, there have Operations (INPO) (Reference 2)

recent report by the Institute of Nuclear Power This information notice pro- provides additional information on this subject. and discusses degraded fuel

vides information on some of the subsequent eventsfuel reconstitution as major

and a lack of proper radiological control during learned also are included.

sources of hot particles. Generic licensee lessons

information for applicability

It is expected that recipients will review this to preclude a similar

to their facilities and consider action, if appropriate, suggestions contained in this

problem occurring at their facilities. However, no specific action or

notice do not constitute NRC requirements; therefore, written response is required.

Discussion:

hot particle exposures were

During the first 6 months of 1987, events involving Two events in late 1986 (at

reported at nine different nuclear power stations. exceeding NRC regula- V.C. Summer and San Onofre) involved exposures apparentlyof eight of these

tory limits. Attachment 1 provides summary descriptions from the referenced inspec- events. More detailed descriptions can be obtained Reports are available

tion reports for each event. (Copies of NRC Inspection Washington, D.C.)

from the NRC Public Document Room, 1717 H Street N.W.,

degraded fuel and neutron- Hot particles come primarily from two major sources: While much of the

activated corrosion and wear products (e.g., Stellite). corrosion

information in this notice is pertinent to both neutron-activated

as activated particles) and

and wear product particles (hereafter referred to

K> QIN 87-39 August 21, 1987 irradiated fuel particles (hereafter referred

to as fuel particles), a major

concern of this notice is extended facility operation

the resulting problems with fuel particle contamination. with degraded fuel and

NRC review of licensees' corrective actions, discussions On the basis of an

operating staffs, and information obtained by with licensees'

NRC inspectors, the lessons

learned and licensee good practices resulting

from the events summarized in

Attachment 1 are as follows:

1. Extended power plant operation with degraded fuel

result in widespread dispersal of fuel particles. (leaking fuel pins) can

experience fuel particle contamination problems Some plants continue to

pins have been removed because of the residual long after leaking fuel

systems. Some plants with these problems have contamination of plant

for missing fuel pellets and fragments and to started programs to account

identify measures to recover

this material.

2. Considerations concerning the handling of leaking

following: fuel include the

a. Special techniques and precautions for handling

are necessary to prevent aggravating the spread leaking fuel bundles

For example, containment devices should be used of fuel particles.

fuel. The lack of proper radiological controls when reconstituting

fuel reconstitution process in the San Onofre and oversight of the

3 fuel pool led to loss

of control and dispersal of numerous fuel particles

Fuel particles then spread through the plant spent into the pool.

to the liquid radwaste systems. fuel systems and

b. A damaged, leaking fuel pin that is not properly

segregated from the common fuel pool area could contained and

long-term source of fuel particle contamination. be a significant, c. Plants should be aware that NSSS vendors' special

refueling tools and

equipment could be a source of fuel particle contamination.

tools and equipment should be carefully surveyed These

and before they are shipped to other facilities. before they are used

3. Some plants that have operated for extended periods

fuel and plants with activated particle problems of time with degraded

specialized, comprehensive training programs for now have instituted

workers and general employees. These programs plant system maintenance

inform and prepare the plant staff to cope with are designed to better

particle problems. Additionally, as part of the continuing fuel

comprehensive

control programs, special new procedures to improve contamination

surveys for detection

--

. .IN 87-39 August 21, 1987 of.hot particles have been prepared and health physics technicians have

been trained in their use. Decontamination and dose evaluation methods

and procedures that focus on hot particles have been implemented. (See

summaries of events at Trojan and.San Onofre in Attachment 1.)

.4.. In general, ;licensees have upgraded their programs for contamination

monitoring of "clean," laundered anti-contamination protective clothing

(PC). However, PC continues to be a means of transferring both fuel

particles and activated particles. Some facilities need to consider

making their PC monitoring programs more sensitive. For example, some

licensees that are using contractor laundry services found the contrac- tor's alarm on the radiation monitor (used to screen PC) too high to

-detect 0.4 microcurie (VCi) particles. Moreover, when commercial plant laundry

services are used, it is possible that PC from a "particle-free"

  • *-can be mixed with PC from a plant with hot particle problems. Finally, at.leastrone licensee was relying solely on monitoring of large bundles

of washed PC (bulk surveys) and was not monitoring samples of individual

PC. For plants with identified particle problems, individual PC items

may have to be checked before they are reused after cleaning.

5. Except for the-Trojan event discussed in Attachment 1, to date, no

licensee has reported detecting hot.particles during airborne sampling.

However, as a precaution,,some licensees have elected to provide workers

with respiratory protection for performing maintenance on plant systems

known to-be a source of hot particles. No plant has reported inhalation

or ingestion of hot particles by any worker.

6. Hot particles in contact with skin.produce very high dose rates. Diligent

personnel contamination surveys performed as soon as practical after .

completing work involving contamination are needed to minimize potential

exposure times.-

7. Approximately 75 percent of the U.S. power reactor facilities are cur- rently using new high-sensitivity whole-body contamination monitors.

These state-of-the-art contamination monitors increase the probability of

detecting hot-particles on plant personnel while reducing the likelihood

of inadvertently releasing particles from the plant site. To-date, most

of-the particles found on personnel have:been detected by these new

monitors. Even with use of the new monitors, a few instances have oc- curred where hot particles have inadvertently been carried home by workers

. and have-been detected in the home or on the worker returning to the site.

No significant ,public exposures have been reported to date.

8. In a recent study for the NRC (Reference 3), it was reported that a plant

operating with 0.125 percent pin-hole fuel cladding defects showed a

general five-fold increase in whole-body radiation exposure rates in some

IN 87-39 .

August 21, 1987 areas of the plant when compared to a sister plant with

fuel (<0.01percent leakers). Around certain plant systems high-integrity

fuel may elevate.-radiation exposure rates even more. the degraded

-

9. Maintenance-on valves with Stellite components can cause

cobalt-containing debris with Co-60 as the resultant introduction of

product. Some plants have instituted work controls (e.g.,neutron activation

ment and post-maintenance cleaning) to minimize this input use of contain- systems (Reference 4). into reactor

Health Implications and Radiation Protection Criteria

for Hot Particle- Exposures of Skin: -

A hot'particle on the skin gives a high beta dose to

a small area.' Any radia- tion dose to the skin is-assumed to result in'some increased

cancer, although'this type of cancer is rarely fatal.' risk of skin

indicate that highly localized irradiation of-the skin'by Experiments with animals

likely to'cause skin cancer than more uniform irradiation hot particles is less

of radioactive material.:- by the same quantity

In addition to any increased risk of cancer, large

particles also may produce observable effects such doses to the skin from hot

as reddening, hardening, peeling, or ulceration of the skin-immediately around

effects appear only'after a-threshold dose is exceeded.the particle; These

particles 'equired to-produce these effects'in the 'skin The doses from hot

cisely;-Ihowever, -it appears likely, except for a point are'not known pre- effects will only be seen for doses of hundreds of rems reddening,-that these

effects have been seen to date on any workers who have or more.'- No such

particles, even though one exposure has been measured been exposed to-hot

512 rem. or calculated as high as

Recent reviews of radiobiology and radiation protection

cluding considerations of hot particle exposures, have criteria for skin, in- been provided-by-Wells

(Reference 5) and Charles (References 6 and 7).

The NRC staff recognizes the need for more'information

radiation on skin and particularly the effects-of hot on the effects of

The staff has requested the National Council on Radiation particle irradiation.

Measurements (NCRP) to. study the health significance of Protection and

and to provisde recommendations- based on the findings of hot particle exposures

recommendations may result in changes in NRC requirements this study. These

particle exposures. However, until these requirements with respect to hot

are changed, IE Infor- mation Notice 86-23 (Reference 1) contains current information

evaluating doses to skin resulting from hot particles. for use in

./ .. IN 87-39 August. 21, 1987 Page 5 of S

oI specific action or.written response is required by this information notice.

  • you have any questions about this matter, please contact the Regional

Admiistrator 'f the appropriate regional office or this office.

e,

.harles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technwcal Contact:- James E..Wigginton, NRR

(301) 492-4663 John D. Buchanan, NRR

.(301) 492-7293 References

I. JAE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tihn With Hot Particles," April 9, 1986.

2i. nstitute of Nuclear Power Operations, Significant Event Report 18-87 (Rev..2), "Radiation Exposure From Small Particles," July 16, 1987.

3,- Hoeller; M. P., :G. F. Martin, and D. L..Haggard, "The Impact of Fuel

  • -Cladding Failure Events on Occupational Radiation Exposures at Nuclear
PowerPants. Case Study: PWR During RoutineOperations," NUREG/CR-4485 (PNL-5606), January 1986.

Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From

H4

.`Valve IMaintenance," Electric Power Research Institute, EPRI NP-3220, Final

Report, August 1983. .

5.. Welli, 3., "Problems Associated With Localized Skin Exposures," in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a

. Workshop. heldat Saclay, France, on October 9-11, 1985, Brit.

.J3. Radiology, Supplement No. 19, pp. 146-150 (1986).

  • .6. Charles, 4.W., "The Biological Bases of Radiation Protection Criteria for

Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta

Particles and Low Energy X-Rays," Proceedings of a Workshop held at

Sacay, Francei October 7-9,-1985," Radiation Protection Dosimetry 14 (No.

-

79-90 (1986).

P2),pp.

-7. Charles, 14. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent

. .Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).

Attachments;.. ..

-l.*. EventSummaries

.2.. List-4f Recently Issued NRC Information Notices

Attachment 1 IN 87-39 August 21, 1987 EVENT SUMMARIES

San Onofre 3. Events Durina November 1986 - March 1987, Inspection Report

No. 50-362/86-37 Background:

At the onset of the first fuel cycle, significant fuel degradation was evident.

The plant continued to operate with approximately 105 defective fuel pins. In

late 1985 during the first refueling outage, a fuel pin was inadvertently

pulled apart during the fuel reconstitution process. Several fuel pellets fell

and dispersed throughout the fuel pool. Fuel particles had previously been

detected early on during reconstitution on fuel handling tools and on the

refueling floors. All the severely damaged fuel pins were then grouped into

one fuel bundle and stored in the pool without any containment.

Event Specifics:

From January 2 through February 20, 1987, the licensee's aggressive hot parti- cle inventory and tracking system indicated that 92 "new" fuel particles

(recently neutron irradiated), 155 "old" fuel particles, 51 ruthenium, 84 crud, and 42 cobalt particles had been found and analyzed. Before 1987, no formal

tracking program existed.

Several incidents involving hot particles have occurred, including an apparent

worker extremity exposure (hand) of 512 rem during November 1986. As a result, appropriate NRC enforcement actions are currently underway. Three events

involving the inadvertent release of hot particles from the plant site occurred

in February 1987. In two of these events, the radiation dose to the public was

determined to be negligible. However, the third event involved a 0.2.;Ci

particle found by a worker at his home during a self-initiated radiological

survey. The licensee has not yet estimated the potential dose to the worker's

family as a result of this occurrence.

In the licensee's licensee event report (LER No.86-015, Revision 1) of Febru- ary 22, 1987, the following program improvements for detecting hot particles

and controlling personnel exposures from hot particles were described:

f

Extensive, mandatory use of exceedingly sensitive fixed instrumentation

(frisking booths) for the detection of personnel contamination;

Special training (including hands-on laboratory exercises) in radioactive

particle characteristics and survey techniques for all Health Physics

Technicians;

C-.

Attachment 1 IN 87-39 August 21, 1987 Oral and written indoctrination of all managers, first line super- visors and workers in the special problems associated with radio- active particles, including the methods each person must employ to

protect himself;

Special procedures to assure detection and control of radioactive

particles which feature the establishment of a clearly identifiable

zone, to demark and contain such particles, surrounded by clearly

identified buffer zones (or solid physical barriers) which are

surveyed frequently to verify that control is being maintained;

Maintenance and wide publication of a radioactive particle census

during outages to maintain station awareness;

The establishment of a Task Force to recommend and implement action to

minimize the future production and movement of radioactive particles.

Trojan, April, 1987, Inspection Report No. 50-344/87-15 Background:

The facility has operated since July 1982 with an estimated 112 fuel pellets

unaccounted for throughout the reactor and support plant systems. The licensee

recovered or located about 264 pellets of the estimated 376 missing after the

1982 refueling outage, which occurred because of the baffle jetting problems of

the 1981 fuel cycle. (See IE Information Notice 82-27, "Fuel Rod Degradation

Resulting From Baffle.Water-Jet Impingement," August .5, 1982.)

Event Specifics:

Shortly after the start of the 1987 refueling outage in April, a significant

increase in personnel skin contaminations occurred. On April 9, high surface

contamination (up to 300,000 dpm/100 cm2) and high airborne activity levels

-.(2E-7 pCi/cc, mixed fission products) in containment resulted from the dis- persal of fuel fragments during reactor vessel. stud removal and stud-hole

plugging operations. The workers in the reactor cavity were wearing respira- tors and no excessive uptakes of.radioactive materials were detected during

followup whole-body counting. Because of the spread of contamination to the

spent fuel building, the licensee stopped all- reactor building cavity work and

all personnel evacuated the area that afternoon.

On April 10, a licensee radiation survey located a hot spot on the cavity floor

near a reactor vessel stud-hole (>100 rad/hr beta and 30 R/hr gamma contact

reading using a portable ion-chamber survey.instrument). On April 11, another

worker located what appeared to be about one-half of a fuel pellet in the

flange area at the stud hole. This partial fuel pellet was removed on

April 12.

Attachment 1 IN 87-39 August 21, 1987 On April 17, a radiation protection technician, after performing a survey of

the lower refueling cavity, discovered a fuel particle lodged in his protective

rubber shoe cover. This particle was later determined to be composed of

approximately 50 mCi of mixed fission product activity; showed readings of 1200

mR/hr with the window open and 250 mR/hr with the window closed. After a

careful time-and-motion study of the technician's activities, the licensee

determined that no NRC regulatory dose limits were exceeded. (Licensee esti- mates were 1.2 rem to whole body; 4.6 rem to skin; 9.6 rem to extremities.)

In general, it appears that the licensee experienced a programmatic breakdown

that resulted in several workers receiving significant, unnecessary radiation

exposures from fuel particle contamination. In LER No. 87-08'dated May 8, 1987, the licensee identified the following additional concerns and'corrective

actions. The LER stated in part:

Workers entering containment on April 9 were not-aware of the fuel

particle hazards. As a corrective measure, all personnel with

access to radiological control areas were retrained to be informed of

the fuel particle problem and perform hands-on training to demonstrate

competence in anti-contamination clothing use. Daily reports

are being provided to workers on the status of containment activities.

Radiation surveys and record keeping were inadequate. As a corrective

measure, new procedures were developed to specifically address

discrete radioactive particles. All radiation protection technicians

have been trained on these new procedures...

There was-insufficient extremity monitoring and no procedures for

particle control. As a corrective measure, procedures have been

prepared to address particle control. Additional extremity moni- toring is being utilized.

Evaluation of radiological events needs to be improved. A'new-pro

cedure will be prepared for documenting and evaluating radiologicalj :

events.-

Review of radiation protection activities.'is insufficient. A new

separate onsite review committee will be established to evaluate

radiological events and to routinely review the performance of the

Radiation Protection Department. -

Insufficient staffing existed. Increasing the manpower in both the

onsite Radiation Protection Department and the corporate Radiological

Safety Branch of the Nuclear Safety and Regulation Department is being

pursued.

Attachment 1 IN 87-39 August 21, 1987 Problems existed due to insufficient radiation monitoring and surveying

equipment. Additional equipment including new portal monitors and

radiation monitoring equipment has been procured.

There was the potential for radiation exposure to individuals from fuel

particles on anti-contamination clothing. An evaluation for potential

exposure is in progress.

V. C. Summer, November 1986, Inspection Report No. 50-395/86-22 After working-in a "clean" area where no protective clothing was required, contamination was detected on the hand of an electrician who had worked on a

control panel for the overhead crane in the fuel handling building. After

measuring the dose rates (window open and window closed) with a portable survey

instrument the worker's hand was decontaminated. The contaminant was not

retained for further analysis. Based on the survey instrument readings, the

dose to the workers hand was calculated to be about 420 rems (at a depth of

7 mg/cm 2 2 averaged over an area of 1 cm ).

Salem Unit 2, April 1987, Inspection Report No. 50-311/87-11 A fuel particle was detected by a whole-body contamination monitor on a work- er's arm. The particle was identified as a fuel particle (about 225 days since

in core) by using a gamma-ray spectrometer [Ge(Li) detector]. The licensee

believes that the source of the particle was from the last refueling outage

about 8 months earlier.

Yankee Nuclear Power Station, May 1987, Inspection Report No. 50-29/87-10

A potential skin exposure of 7.6 rem to a worker's scalp occurred from an

activated particle. The apparent source of the particle was the worker's PC

hood. After its discovery, the particle remained on the worker's scalp for

about 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, awaiting medical assistance to remove the particle. Prior to

medical assistance arriving on site, the particle was removed by shaving the

hair. Earlier in May, the licensee reported that, during fuel assembly move- ment, pieces of fuel rods were seen to have fallen away from the assembly and

land on top of the reactor core and in the refueling cavity area. Fuel recon- stitution was in progress. -

Attachment 1 IN 87-39 August 21, 1987 Indian Point Unit 3, May 1987, Inspection Report No. 50-286/87-18 A maintenance foreman exiting the containment after helping to replace steam

generator manway covers received an estimated 4 rem dose to the skin (in back

of neck) from an activated zirconium particle. It appears the particle dis- lodged from his PC hood and fell on his neck during temporary removal of the

hood during a work rest-break.

Quad Cities/Dresden/Zion, 1986 and 1987 A special program to investigate hot particle incidents has been in place at

these Commonwealth Edison Company facilities for the last 1-2 years. A total

of approximately 100 individual hot particles were found on workers' skin or

clothing in 1986. Approximately 130 particles were found in the first six

months of 1987. The particles have been predominantly Co-60 with activities

ranging from about 0.01 to 1 pCi. Those particles were analyzed for physical

size; the smallest was 20 microns. The licensee investigated each event and

calculated skin doses. No overexposures have been reported. The transfer

mechanism of the particles to the workers has not been positively identified.

Callaway Station, 1986 Period, Report No. 50-483/8700 (DRSS)

The licensee experienced ten hot particle skin contamination incidents primari- ly during the refueling outage early during the year. No NRC dose limits were

exceeded. Ineffective frisking (hand-held pancake GM-tube) of laundered PC and

potentially degraded dry-cleaning fluid quality (leading to cross-contami- nation of PC during cleaning) were identified by the licensee as possible

contributors to this contamination problem.

Attachment 2 IN 87-39 August 21, 1987 LIST OF RECENTLY ISSUED

INFORMATION NOTICES 1987

Information Date of

Notice No. Subject Issuance Issued to

87-38 Inadequate or Inadvertent 8/17/87 All nuclear power

Blocking of Valve Movement reactor facilities

holding an OL or CP.

87-37 Compliance with the General 8/10/87 All persons specifi- License Provisions of cally licensed to

10 CFR Part 31 manufacture or to

initially transfer

devices containing

radioactive material

to general licensees, as defined in 10 CFR

Part 31.

87-36 Significant Unexpected 8/4/87 All nuclear power

Erosion of Feedwater Lines reactor facilities

holding an OL or CP.

87-35 Reactor Trip Breaker, 7/30/87 All nuclear power

Westinghouse Model DS-416, reactor facilities

Failed to Open on Manual holding an OL or

Initiation from the Control CP employing W DS-416 Room reactor trip breakers.

87-34 Single Failures in Auxiliary 7/24/87 All holders of an

Feedwater Systems OL or a CP for

pressurized water

reactor facilities.

87-33 Applicability of 10 CFR 7/24/87 All NRC licensees.

Part 21 to Nonlicensees

87-32 Deficiencies in the Testing 7/10/87 All nuclear power

of Nuclear-Grade Activated reactor facilities

Charcoal. holding an OL or CP.

87-31 Blocking, Bracing, and 7/10/87 All NRC licensees.

Securing of Radioactive

Materials Packages in

Transportation.

. :

OL = Operating License

CP = Construction Permit

- .V IN 87-XX

August, 1987 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate regional office or this office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

James E. Wigginton, NRR

(301) 492-4663 John 0. Buchanan, NRR

(301) 492-7293 References

1. IE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tion With Hot Particles," April 9, 1986.

2. Institute of Nuclear Power Operations, Significant Event Report 18-87 (Rev. 2), "Radiation Exposure From Small Particles," July 16, 1987.

3. Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel

Cladding Failure Events on Occupational Radiation Exposures at Nuclear

Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.

4. Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From

Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final

Report, August 1983.

5. Wells, J., "Problems Associated With Localized Skin Exposures," in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a

Workshop held at Saclay, France, on October 9-11, 1985, Brit.

J. Radiology, Supplement No. 19, pp. 146-150 (1986).

6. Charles, M. W,., "The Biological Bases of Radiation Protection Criteria for

Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta

Particles and Low Energy X-Rays," Proceedings of a Workshop held at

Saclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.

2), pp. 79-90 (1986).

7. Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and Recent

Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).

Attachments:

1. Events Summaries

2. List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES p g C

/OGCB:DOEA:NRR

z UERidlHBerlinger

RBDE-R

PN R n 1 847 4 S8//' 87 8/ /87 RPB:DREP:NRR *RP:DREP:NRR R P:NR '*D:DREP:NRR *PPMB:ARM

JEWigginton JDBuchanan LJCunningham FJCongel TechEd

7/28/87 7/28/87 7/28/87 7/28/87 7/28/87

IN 87-XX

August, 1987 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate regional office or this office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

James E. Wigginton, NRR

(301) 492-4663 John D. Buchanan, NRR

(301) 492-7293 References

1. "IE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tion With Hot Particles," April 9, 1986.

2. Institute of Nuclear Power Operations, Significant Event Report 18-87 (Rev. 2), "Radiation Exposure From Small Particles," July 16, 1987.

3. Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel

Cladding Failure Events on Occupational Radiation Exposures at Nuclear

Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.

4. Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From

Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final

Report, August 1983.

5. Wells, J., "Problems Associated With Localized Skin Exposures," in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a

Workshop held at Saclay, France, on October 9-11, 1985, Brit.

J. Radiology, Supplement No. 19, pp. 146-150 (1986).

6. Charles, M. W., "The Biological Bases of Radiation Protection Criteria for

Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta

Particles and Low Energy X-Rays," Proceedings of a Workshop held at

Saclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.

2), pp. 79-90 (1986).

7. Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and

Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.

69-81 (1986).

Attachments:

1. Events Summaries

2. List of Recently Issued

NRC Information Notices

  • SEE PREVIOUS CONCURRENCES D/DOEA:NRR C/OGCB:DOEA:NRR

CERossi CHBerlinger

8/ /87 8/10/87

  • RPB:DREP:NRR *RPB:DREP:NRR *AC:RPB:DREP:NRR *D:DREP:NRR *PPMB:ARM

JEWigginton JDBuchanan LJCunningham FJCongel TechEd

7/28/87 7/28/87 7/28/87 7/28/87 7/28/87

~'V IN 87-XX

August, 1987 No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the Regional

Administrator of the appropriate regional office or this office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

James E. Wigginton, NRR

(301) 492-4663 John D. Buchanan, NRR

(301) 492-7293 References

1. "IE Information Notice 86-23, "Excessive Skin Exposures Due to Contamina- tion With Hot Particles," April 9, 1986.

2. Institute of Nuclear Power Operations, Significant Event Report 18-87 (Rev. 2), "Radiation Exposure From Small Particles," July 16, 1987.

3. Moeller, M. P., G. F. Martin, and D. L. Haggard, "The Impact of Fuel

Cladding Failure Events on Occupational Radiation Exposures at Nuclear

Power Plants. Case Study: PWR During Routine Operations," NUREG/CR-4485 (PNL-5606), January 1986.

4. Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting From

Valve Maintenance," Electric Power Research Institute, EPRI NP-3220, Final

Report, August 1983.

5. Wells, J., "Problems Associated With Localized Skin Exposures,' in "Radia- tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of a

Workshop held at Saclay, France, on October 9-11, 1985, Brit.

J. Radiology, Supplement No. 19, pp. 146-150 (1986).

6. Charles, M. W., "The Biological Bases of Radiation Protection Criteria for

Superficial, Low Penetrating Radiation Exposure," in "Dosimetry of Beta

Particles and Low Energy X-Rays," Proceedings of a Workshop held at

Saclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.

2), pp. 79-90 (1986).

7. Charles, M. W., "Skin, Eye, and Testis: Current Exposure Problems and

Recent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.

69-81 (1986).

Attachments:

1. Events Summaries

2. List of Recently Issued

NRC Information Notices

C/OGCB:DOEA:NRF

CHBerlinger

R i EP:NRR RPM :NRR A REP:NRR D:DREP:NRRI

JEigginton J. an LJC I4nningham FJCongel Techd

7/&X/87 7/ig/87 7}(%/87 -4/ti/8 7 7/w