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

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{{#Wiki_filter:..-.iV' 'SINS No.: 6835iN 87-39UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555August 21, 1987NRC INFORMATION NOTICE NQ. 87-39: CONTROL OF HOT PARTICLE CONTAMINATIONAT NUCLEAR POWER PLANTS
{{#Wiki_filter:..-.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==
==Addressees==
:All nuclear power reactor facilities and spent fuel storage facilities holdingan NRC license or a construction permit.Background and
:
All nuclear power reactor facilities
 
and spent fuel storage facilities
 
holding an NRC license or a construction
 
permit.Background
 
and


==Purpose==
==Purpose==
:IE Information 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). Sincethat information notice was issued, there have been more of these events, and arecent 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 fueland a lack of proper radiological control during fuel reconstitution as majorsources of hot particles. Generic licensee lessons learned also are included.It is expected that recipients will review this information for applicabilityto their facilities and consider action, if appropriate, to preclude a similarproblem occurring at their facilities. However, suggestions contained in thisnotice do not constitute NRC requirements; therefore, no specific action orwritten response is required.Discussion:During the first 6 months of 1987, events involving hot particle exposures werereported at nine different nuclear power stations. Two events in late 1986 (atV.C. Summer and San Onofre) involved exposures apparently exceeding NRC regula-tory limits. Attachment 1 provides summary descriptions of eight of theseevents. More detailed descriptions can be obtained from the referenced inspec-tion reports for each event. (Copies of NRC Inspection Reports are availablefrom 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 theinformation in this notice is pertinent to both neutron-activated corrosionand wear product particles (hereafter referred to as activated particles) and
: IE Information
 
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
 
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
 
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.
 
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 high-integrity
 
fuel (<0.01percent
 
leakers).
 
Around certain plant systems the degraded fuel may elevate.-radiation
 
exposure rates even more. -9. Maintenance-on
 
valves with Stellite components
 
can cause introduction
 
of cobalt-containing
 
debris with Co-60 as the resultant
 
neutron activation
 
product. Some plants have instituted
 
work controls (e.g., use of contain-ment and post-maintenance
 
cleaning)
to minimize this input into reactor systems (Reference
 
4).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
 
risk of skin cancer, although'this
 
type of cancer is rarely fatal.' Experiments
 
with animals indicate that highly localized
 
irradiation
 
of-the skin'by hot particles
 
is less likely to'cause skin cancer than more uniform irradiation
 
by the same quantity of radioactive
 
material.:-
In addition to any increased
 
risk of cancer, large doses to the skin from hot particles
 
also may produce observable
 
effects such as reddening, hardening, peeling, or ulceration
 
of the skin-immediately
 
around the particle;
These effects appear only'after
 
a-threshold
 
dose is exceeded.
 
The doses from hot particles
 
'equired to-produce
 
these effects'in
 
the 'skin are'not known pre-cisely;-Ihowever, -it appears likely, except for a point reddening,-that
 
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
 
as high as 512 rem.Recent reviews of radiobiology
 
and radiation
 
protection
 
criteria for skin, in-cluding considerations
 
of hot particle exposures, have been provided-by-Wells (Reference
 
5) and Charles (References
 
6 and 7). ''The NRC staff recognizes
 
the need for more'information
 
on the effects of radiation
 
on skin and particularly
 
the effects-of
 
hot particle irradiation.
 
The staff has requested
 
the National Council on Radiation
 
Protection
 
and Measurements (NCRP) to. study the health significance
 
of hot particle exposures and to provisde recommendations- based on the findings of this study. These recommendations
 
may result in changes in NRC requirements
 
with respect to hot particle exposures.
 
However, until these requirements
 
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
 
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.H4 Heard, D. B., and R. J. Freeman, "Cobalt Contamination
 
Resulting
 
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
 
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.P2),pp. 79-90 (1986).-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 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...
 
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 averaged over an area of 1 cm 2).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 hours, 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 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
 
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
 
C p g /OGCB:DOEA:NRR
 
z UERidlHBerlinger
 
RBDE-R R PN 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


K> QIN 87-39August 21, 1987 irradiated fuel particles (hereafter referred to as fuel particles), a majorconcern of this notice is extended facility operation with degraded fuel andthe resulting problems with fuel particle contamination. On the basis of anNRC review of licensees' corrective actions, discussions with licensees'operating staffs, and information obtained by NRC inspectors, the lessonslearned and licensee good practices resulting from the events summarized inAttachment 1 are as follows:1. Extended power plant operation with degraded fuel (leaking fuel pins) canresult in widespread dispersal of fuel particles. Some plants continue toexperience fuel particle contamination problems long after leaking fuelpins have been removed because of the residual contamination of plantsystems. Some plants with these problems have started programs to accountfor missing fuel pellets and fragments and to identify measures to recoverthis material.2. Considerations concerning the handling of leaking fuel include thefollowing:a. Special techniques and precautions for handling leaking fuel bundlesare necessary to prevent aggravating the spread of fuel particles.For example, containment devices should be used when reconstitutingfuel. The lack of proper radiological controls and oversight of thefuel reconstitution process in the San Onofre 3 fuel pool led to lossof control and dispersal of numerous fuel particles into the pool.Fuel particles then spread through the plant spent fuel systems andto the liquid radwaste systems.b. A damaged, leaking fuel pin that is not properly contained andsegregated 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 andequipment could be a source of fuel particle contamination. Thesetools and equipment should be carefully surveyed before they are usedand before they are shipped to other facilities.3. Some plants that have operated for extended periods of time with degradedfuel and plants with activated particle problems now have institutedspecialized, comprehensive training programs for plant system maintenanceworkers and general employees. These programs are designed to betterinform and prepare the plant staff to cope with the continuing fuelparticle problems. Additionally, as part of comprehensive contaminationcontrol programs, special new procedures to improve surveys for detection
Criteria for Superficial, Low Penetrating


: --..IN 87-39August 21, 1987 of.hot particles have been prepared and health physics technicians havebeen trained in their use. Decontamination and dose evaluation methodsand procedures that focus on hot particles have been implemented. (Seesummaries of events at Trojan and.San Onofre in Attachment 1.).4.. In general, ;licensees have upgraded their programs for contaminationmonitoring of "clean," laundered anti-contamination protective clothing(PC). However, PC continues to be a means of transferring both fuelparticles and activated particles. Some facilities need to considermaking their PC monitoring programs more sensitive. For example, somelicensees 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 laundryservices are used, it is possible that PC from a "particle-free" plant* *-can be mixed with PC from a plant with hot particle problems. Finally,at.leastrone licensee was relying solely on monitoring of large bundlesof washed PC (bulk surveys) and was not monitoring samples of individualPC. For plants with identified particle problems, individual PC itemsmay have to be checked before they are reused after cleaning.5. Except for the-Trojan event discussed in Attachment 1, to date, nolicensee has reported detecting hot.particles during airborne sampling.However, as a precaution,,some licensees have elected to provide workerswith respiratory protection for performing maintenance on plant systemsknown to-be a source of hot particles. No plant has reported inhalationor ingestion of hot particles by any worker.6. Hot particles in contact with skin.produce very high dose rates. Diligentpersonnel contamination surveys performed as soon as practical after .completing work involving contamination are needed to minimize potentialexposure 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 ofdetecting hot-particles on plant personnel while reducing the likelihoodof inadvertently releasing particles from the plant site. To-date, mostof-the particles found on personnel have:been detected by these newmonitors. 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 plantoperating with 0.125 percent pin-hole fuel cladding defects showed ageneral five-fold increase in whole-body radiation exposure rates in some
Radiation


IN 87-39 .August 21, 1987 areas of the plant when compared to a sister plant with high-integrityfuel (<0.01percent leakers). Around certain plant systems the degradedfuel may elevate.-radiation exposure rates even more. -9. Maintenance-on valves with Stellite components can cause introduction ofcobalt-containing debris with Co-60 as the resultant neutron activationproduct. Some plants have instituted work controls (e.g., use of contain-ment and post-maintenance cleaning) to minimize this input into reactorsystems (Reference 4).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 risk of skincancer, although'this type of cancer is rarely fatal.' Experiments with animalsindicate that highly localized irradiation of-the skin'by hot particles is lesslikely to'cause skin cancer than more uniform irradiation by the same quantityof radioactive material.:-In addition to any increased risk of cancer, large doses to the skin from hotparticles also may produce observable effects such as reddening, hardening,peeling, or ulceration of the skin-immediately around the particle; Theseeffects appear only'after a-threshold dose is exceeded. The doses from hotparticles 'equired to-produce these effects'in the 'skin are'not known pre-cisely;-Ihowever, -it appears likely, except for a point reddening,-that theseeffects will only be seen for doses of hundreds of rems or more.'- No sucheffects have been seen to date on any workers who have been exposed to-hotparticles, even though one exposure has been measured or calculated as high as512 rem.Recent reviews of radiobiology and radiation protection criteria for skin, in-cluding considerations of hot particle exposures, have been provided-by-Wells(Reference 5) and Charles (References 6 and 7). ''The NRC staff recognizes the need for more'information on the effects ofradiation on skin and particularly the effects-of hot particle irradiation.The staff has requested the National Council on Radiation Protection andMeasurements (NCRP) to. study the health significance of hot particle exposuresand to provisde recommendations- based on the findings of this study. Theserecommendations may result in changes in NRC requirements with respect to hotparticle exposures. However, until these requirements are changed, IE Infor-mation Notice 86-23 (Reference 1) contains current information for use inevaluating doses to skin resulting from hot particles.
Exposure," in "Dosimetry


./ ..IN 87-39August. 21, 1987Page 5 of So I specific action or. written response is required by this information notice.* you have any questions about this matter, please contact the RegionalAdmiistrator 'f the appropriate regional office or this office.e ,.harles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnwcal Contact:- James E..Wigginton, NRR(301) 492-4663John D. Buchanan, NRR.(301) 492-7293ReferencesI. 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.H4 Heard, D. B., and R. J. Freeman, "Cobalt Contamination Resulting 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 forSuperficial, Low Penetrating Radiation Exposure," in "Dosimetry of BetaParticles and Low Energy X-Rays," Proceedings of a Workshop held at-Sacay, Francei October 7-9,-1985," Radiation Protection Dosimetry 14 (No.P2),pp. 79-90 (1986).-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
of Beta Particles


Attachment 1IN 87-39August 21, 1987 EVENT SUMMARIESSan Onofre 3. Events Durina November 1986 -March 1987, Inspection ReportNo. 50-362/86-37Background:At the onset of the first fuel cycle, significant fuel degradation was evident.The plant continued to operate with approximately 105 defective fuel pins. Inlate 1985 during the first refueling outage, a fuel pin was inadvertentlypulled apart during the fuel reconstitution process. Several fuel pellets felland dispersed throughout the fuel pool. Fuel particles had previously beendetected early on during reconstitution on fuel handling tools and on therefueling floors. All the severely damaged fuel pins were then grouped intoone 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 formaltracking program existed.Several incidents involving hot particles have occurred, including an apparentworker extremity exposure (hand) of 512 rem during November 1986. As a result,appropriate NRC enforcement actions are currently underway. Three eventsinvolving the inadvertent release of hot particles from the plant site occurredin February 1987. In two of these events, the radiation dose to the public wasdetermined to be negligible. However, the third event involved a 0.2.;Ciparticle found by a worker at his home during a self-initiated radiologicalsurvey. The licensee has not yet estimated the potential dose to the worker'sfamily 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 particlesand controlling personnel exposures from hot particles were described:fExtensive, mandatory use of exceedingly sensitive fixed instrumentation(frisking booths) for the detection of personnel contamination;Special training (including hands-on laboratory exercises) in radioactiveparticle characteristics and survey techniques for all Health PhysicsTechnicians;C-.
and Low Energy X-Rays," Proceedings


Attachment 1IN 87-39August 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 toprotect himself;Special procedures to assure detection and control of radioactiveparticles which feature the establishment of a clearly identifiablezone, to demark and contain such particles, surrounded by clearlyidentified buffer zones (or solid physical barriers) which aresurveyed frequently to verify that control is being maintained;Maintenance and wide publication of a radioactive particle censusduring outages to maintain station awareness;The establishment of a Task Force to recommend and implement action tominimize the future production and movement of radioactive particles.Trojan, April, 1987, Inspection Report No. 50-344/87-15Background:The facility has operated since July 1982 with an estimated 112 fuel pelletsunaccounted for throughout the reactor and support plant systems. The licenseerecovered or located about 264 pellets of the estimated 376 missing after the1982 refueling outage, which occurred because of the baffle jetting problems ofthe 1981 fuel cycle. (See IE Information Notice 82-27, "Fuel Rod DegradationResulting From Baffle.Water-Jet Impingement," August .5, 1982.)Event Specifics:Shortly after the start of the 1987 refueling outage in April, a significantincrease in personnel skin contaminations occurred. On April 9, high surfacecontamination (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-holeplugging operations. The workers in the reactor cavity were wearing respira-tors and no excessive uptakes of.radioactive materials were detected duringfollowup whole-body counting. Because of the spread of contamination to thespent fuel building, the licensee stopped all- reactor building cavity work andall personnel evacuated the area that afternoon.On April 10, a licensee radiation survey located a hot spot on the cavity floornear a reactor vessel stud-hole (>100 rad/hr beta and 30 R/hr gamma contactreading using a portable ion-chamber survey.instrument). On April 11, anotherworker located what appeared to be about one-half of a fuel pellet in theflange area at the stud hole. This partial fuel pellet was removed onApril 12.
of a Workshop held at Saclay, France, October 7-9, 1985," Radiation


Attachment 1IN 87-39August 21, 1987 On April 17, a radiation protection technician, after performing a survey ofthe lower refueling cavity, discovered a fuel particle lodged in his protectiverubber shoe cover. This particle was later determined to be composed ofapproximately 50 mCi of mixed fission product activity; showed readings of 1200mR/hr with the window open and 250 mR/hr with the window closed. After acareful time-and-motion study of the technician's activities, the licenseedetermined 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 breakdownthat resulted in several workers receiving significant, unnecessary radiationexposures from fuel particle contamination. In LER No. 87-08'dated May 8, 1987,the licensee identified the following additional concerns and'correctiveactions. The LER stated in part:Workers entering containment on April 9 were not-aware of the fuelparticle hazards. As a corrective measure, all personnel withaccess to radiological control areas were retrained to be informed ofthe fuel particle problem and perform hands-on training to demonstratecompetence in anti-contamination clothing use. Daily reportsare being provided to workers on the status of containment activities.Radiation surveys and record keeping were inadequate. As a correctivemeasure, new procedures were developed to specifically addressdiscrete radioactive particles. All radiation protection technicianshave been trained on these new procedures...There was-insufficient extremity monitoring and no procedures forparticle control. As a corrective measure, procedures have beenprepared 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 newseparate onsite review committee will be established to evaluateradiological events and to routinely review the performance of theRadiation Protection Department. -Insufficient staffing existed. Increasing the manpower in both theonsite Radiation Protection Department and the corporate RadiologicalSafety Branch of the Nuclear Safety and Regulation Department is beingpursued.
Protection


Attachment 1IN 87-39August 21, 1987 Problems existed due to insufficient radiation monitoring and surveyingequipment. Additional equipment including new portal monitors andradiation monitoring equipment has been procured.There was the potential for radiation exposure to individuals from fuelparticles on anti-contamination clothing. An evaluation for potentialexposure is in progress.V. C. Summer, November 1986, Inspection Report No. 50-395/86-22After working-in a "clean" area where no protective clothing was required,contamination was detected on the hand of an electrician who had worked on acontrol panel for the overhead crane in the fuel handling building. Aftermeasuring the dose rates (window open and window closed) with a portable surveyinstrument the worker's hand was decontaminated. The contaminant was notretained for further analysis. Based on the survey instrument readings, thedose to the workers hand was calculated to be about 420 rems (at a depth of7 mg/cm2 averaged over an area of 1 cm2).Salem Unit 2, April 1987, Inspection Report No. 50-311/87-11A 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 sincein core) by using a gamma-ray spectrometer [Ge(Li) detector]. The licenseebelieves that the source of the particle was from the last refueling outageabout 8 months earlier.Yankee Nuclear Power Station, May 1987, Inspection Report No. 50-29/87-10A potential skin exposure of 7.6 rem to a worker's scalp occurred from anactivated particle. The apparent source of the particle was the worker's PChood. After its discovery, the particle remained on the worker's scalp forabout 78 hours, awaiting medical assistance to remove the particle. Prior tomedical assistance arriving on site, the particle was removed by shaving thehair. 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 andland on top of the reactor core and in the refueling cavity area. Fuel recon-stitution was in progress. -
Dosimetry
Attachment 1IN 87-39August 21, 1987 Indian Point Unit 3, May 1987, Inspection Report No. 50-286/87-18A maintenance foreman exiting the containment after helping to replace steamgenerator manway covers received an estimated 4 rem dose to the skin (in backof 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 thehood during a work rest-break.Quad Cities/Dresden/Zion, 1986 and 1987A special program to investigate hot particle incidents has been in place atthese Commonwealth Edison Company facilities for the last 1-2 years. A totalof approximately 100 individual hot particles were found on workers' skin orclothing in 1986. Approximately 130 particles were found in the first sixmonths of 1987. The particles have been predominantly Co-60 with activitiesranging from about 0.01 to 1 pCi. Those particles were analyzed for physicalsize; the smallest was 20 microns. The licensee investigated each event andcalculated skin doses. No overexposures have been reported. The transfermechanism 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 wereexceeded. Ineffective frisking (hand-held pancake GM-tube) of laundered PC andpotentially degraded dry-cleaning fluid quality (leading to cross-contami-nation of PC during cleaning) were identified by the licensee as possiblecontributors to this contamination problem.


Attachment 2IN 87-39August 21, 1987LIST OF RECENTLY ISSUEDINFORMATION NOTICES 1987Information Date ofNotice No. Subject Issuance Issued to87-3887-3787-3687-3587-3487-3387-32Inadequate or InadvertentBlocking of Valve MovementCompliance with the GeneralLicense Provisions of10 CFR Part 31Significant UnexpectedErosion of Feedwater LinesReactor Trip Breaker,Westinghouse Model DS-416,Failed to Open on ManualInitiation from the ControlRoomSingle Failures in AuxiliaryFeedwater SystemsApplicability of 10 CFRPart 21 to NonlicenseesDeficiencies in the Testingof Nuclear-Grade ActivatedCharcoal.8/17/878/10/878/4/877/30/877/24/877/24/877/10/877/10/87All nuclear powerreactor facilitiesholding an OL or CP.All persons specifi-cally licensed tomanufacture or toinitially transferdevices containingradioactive materialto general licensees,as defined in 10 CFRPart 31.All nuclear powerreactor facilitiesholding an OL or CP.All nuclear powerreactor facilitiesholding an OL orCP employing W DS-416reactor trip breakers.All holders of anOL or a CP forpressurized waterreactor facilities.All NRC licensees.All nuclear powerreactor facilitiesholding an OL or CP.All NRC licensees.87-31Blocking, Bracing, andSecuring of RadioactiveMaterials Packages inTransportation..:OL =CP =Operating LicenseConstruction Permit
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:
1. Events Summaries 2. List of Recently Issued NRC Information


-.V IN 87-XXAugust, 1987 No specific action or written response is required by this information notice.If you have any questions about this matter, please contact the RegionalAdministrator of the appropriate regional office or this office.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor Regulation
Notices C/OGCB:DOEA:NRF


===Technical Contact:===
CHBerlinger
James E. Wigginton, NRR(301) 492-4663John 0. Buchanan, NRR(301) 492-7293References1. 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 FuelCladding Failure Events on Occupational Radiation Exposures at NuclearPower 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 FromValve Maintenance," Electric Power Research Institute, EPRI NP-3220, FinalReport, August 1983.5. Wells, J., "Problems Associated With Localized Skin Exposures," in "Radia-tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of aWorkshop 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 forSuperficial, Low Penetrating Radiation Exposure," in "Dosimetry of BetaParticles and Low Energy X-Rays," Proceedings of a Workshop held atSaclay, 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 RecentAdvances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp. 69-81 (1986).Attachments:1. Events Summaries2. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCES C p g /OGCB:DOEA:NRRz UERidlHBerlingerRBDE-R R PN n 1 847 4 S8//' 87 8/ /87RPB:DREP:NRR *RP:DREP:NRR R P:NR '*D:DREP:NRR *PPMB:ARMJEWigginton JDBuchanan LJCunningham FJCongel TechEd7/28/87 7/28/87 7/28/87 7/28/87 7/28/87 IN 87-XXAugust, 1987 No specific action or written response is required by this information notice.If you have any questions about this matter, please contact the RegionalAdministrator of the appropriate regional office or this office.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor Regulation


===Technical Contact:===
R i EP:NRR J Eigginton 7/&X/87 RPM :NRR J. an 7/ig/87 A REP:NRR LJC I4nningham
James E. Wigginton, NRR(301) 492-4663John D. Buchanan, NRR(301) 492-7293References1. "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 FuelCladding Failure Events on Occupational Radiation Exposures at NuclearPower 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 FromValve Maintenance," Electric Power Research Institute, EPRI NP-3220, FinalReport, August 1983.5. Wells, J., "Problems Associated With Localized Skin Exposures," in "Radia-tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of aWorkshop 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 forSuperficial, Low Penetrating Radiation Exposure," in "Dosimetry of BetaParticles and Low Energy X-Rays," Proceedings of a Workshop held atSaclay, 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 andRecent Advances in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.69-81 (1986).Attachments:1. Events Summaries2. List of Recently IssuedNRC Information Notices*SEE PREVIOUS CONCURRENCES D/DOEA:NRR C/OGCB:DOEA:NRRCERossi CHBerlinger8/ /87 8/10/87*RPB:DREP:NRR *RPB:DREP:NRR *AC:RPB:DREP:NRR *D:DREP:NRR *PPMB:ARMJEWigginton JDBuchanan LJCunningham FJCongel TechEd7/28/87 7/28/87 7/28/87 7/28/87 7/28/87
~' V IN 87-XXAugust, 1987 No specific action or written response is required by this information notice.If you have any questions about this matter, please contact the RegionalAdministrator of the appropriate regional office or this office.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor Regulation


===Technical Contact:===
7}(%/87 D:DREP:NRRI
James E. Wigginton, NRR(301) 492-4663John D. Buchanan, NRR(301) 492-7293References1. "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 FuelCladding Failure Events on Occupational Radiation Exposures at NuclearPower 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 FromValve Maintenance," Electric Power Research Institute, EPRI NP-3220, FinalReport, August 1983.5. Wells, J., "Problems Associated With Localized Skin Exposures,' in "Radia-tion Damage to Skin: Fundamental and Practical Aspects," Proceedings of aWorkshop 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 forSuperficial, Low Penetrating Radiation Exposure," in "Dosimetry of BetaParticles and Low Energy X-Rays," Proceedings of a Workshop held atSaclay, France, October 7-9, 1985," Radiation Protection Dosimetry 14 (No.2), pp. 79-90 (1986).7. Charles, M. W.,Recent Advances69-81 (1986)."Skin, Eye, and Testis: Current Exposure Problems andin Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.Attachments:1. Events Summaries2. List of Recently IssuedNRC Information NoticesC/OGCB:DOEA:NRFCHBerlingerR i EP:NRRJ Eigginton7/&X/87RPM :NRRJ. an7/ig/87A REP:NRRLJC I4nningham7}(%/87D:DREP:NRRIFJCongel-4/ti/87Techd7/w


}}
FJCongel-4/ti/8 7 Techd 7/w}}


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

Revision as of 13:43, 31 August 2018

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 E
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

All nuclear power reactor facilities

and spent fuel storage facilities

holding an NRC license or a construction

permit.Background

and

Purpose

IE Information

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

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

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.

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 high-integrity

fuel (<0.01percent

leakers).

Around certain plant systems the degraded fuel may elevate.-radiation

exposure rates even more. -9. Maintenance-on

valves with Stellite components

can cause introduction

of cobalt-containing

debris with Co-60 as the resultant

neutron activation

product. Some plants have instituted

work controls (e.g., use of contain-ment and post-maintenance

cleaning)

to minimize this input into reactor systems (Reference

4).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

risk of skin cancer, although'this

type of cancer is rarely fatal.' Experiments

with animals indicate that highly localized

irradiation

of-the skin'by hot particles

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

by the same quantity of radioactive

material.:-

In addition to any increased

risk of cancer, large doses to the skin from hot particles

also may produce observable

effects such as reddening, hardening, peeling, or ulceration

of the skin-immediately

around the particle;

These effects appear only'after

a-threshold

dose is exceeded.

The doses from hot particles

'equired to-produce

these effects'in

the 'skin are'not known pre-cisely;-Ihowever, -it appears likely, except for a point reddening,-that

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

as high as 512 rem.Recent reviews of radiobiology

and radiation

protection

criteria for skin, in-cluding considerations

of hot particle exposures, have been provided-by-Wells (Reference

5) and Charles (References

6 and 7). The NRC staff recognizes

the need for more'information

on the effects of radiation

on skin and particularly

the effects-of

hot particle irradiation.

The staff has requested

the National Council on Radiation

Protection

and Measurements (NCRP) to. study the health significance

of hot particle exposures and to provisde recommendations- based on the findings of this study. These recommendations

may result in changes in NRC requirements

with respect to hot particle exposures.

However, until these requirements

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

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.H4 Heard, D. B., and R. J. Freeman, "Cobalt Contamination

Resulting

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

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.P2),pp. 79-90 (1986).-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 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...

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 averaged over an area of 1 cm 2).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 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

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

C p g /OGCB:DOEA:NRR

z UERidlHBerlinger

RBDE-R R PN 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., Recent Advances 69-81 (1986)."Skin, Eye, and Testis: Current Exposure Problems and in Radiobiology," J. Soc. Radiol. Prot. 6 (No. 2), pp.Attachments:

1. Events Summaries 2. List of Recently Issued NRC Information

Notices C/OGCB:DOEA:NRF

CHBerlinger

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

7}(%/87 D:DREP:NRRI

FJCongel-4/ti/8 7 Techd 7/w