ML20205K856
| ML20205K856 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/19/1986 |
| From: | Hardeman J GEORGIA, STATE OF |
| To: | |
| Shared Package | |
| ML20205K821 | List: |
| References | |
| FOIA-87-76 NUDOCS 8704020056 | |
| Download: ML20205K856 (76) | |
Text
_.. - __
~~~
GeorgiaDepartment of NATURAL RESOURCES l
l LOSS OF SPENT FUEL POOL WATER AT THE I
l EDWIN 1. HATCH NUCLEAR PLANT 4
3 DECEMBER,1986 j
k ' bI5 RESOURCES T
ett ---- A y/ h James L. Setser Chiel Program Coordination Branch F'loyd To er East, suite ISY2 20$ Detter Street. 5 E.
Atlanta, Georgia 30334 (404) 656 4713 i
l N
g Ilk g
1 i
i Environmental Protection Division j
ro2#-Tr7-76 19 DECEMBER,1986 cu l
8704020056 870331
)
hpH f-76 PDR
s d
LOSS OF SPENT FUEL POCL WATER AT THE EDWIN I. HATCH NUCLEAR PLANT
]
3 December,1986 by James C. Hardeman Environmental Radiation Coordinator i
Georgia Department of Natural Resources Environmental Protection Division Environmental Radiation Program 19 December, 1986 e
i
+
4
a
}
Background
The Edwin I. Hatch Nuclear Plant (Plant Hatch) is a two-unit boiling water reactor (BWR) located approximately ten miles north of Baxley, Georgia in l
Appling County, on the southern bank of the Altamaha River.
Plant Hatch is jointly owned by Georgia Power Company (GPC), Oglethorpe Power Corporation, j
the Municipal Electric Authority of Georgia (MEAG) and the City of Dalton, i
and is operated by Georgia Power.
Uni t 1 of Plant Hatch began operation i
in 1975, and Unit II in 1979.
j Event Sequence f
On December 2, 1986, Plant Hatch Unit I was on-line at 100% power.
Unit l
II had been shut down since mid-September for refueling.
At approximately i
10:00 p.m.
a Plant Equipment Operator closed a service air hose station valve which he found cracked open.
The operator was unaware that this valve was the supply isolation valve to the pressure regulator for the spent fuel j
transfer canal inflatable seal.
Over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, air pressure in j
the inflatable seal decreased, eventually dropping to O psig, allowing spent i
fuel pool water to enter the sealing material between the Unit I and Unit i
II Reactor Buildings and between the Reactor Buildings and the Turbine Building.
Several instances of leaking water inside plant buildings were reported between 2:00 p.m.
and 10:00 p.m. on Dece:nber 3, 1986.
Searches for the source of the loss of spent fuel pool water began at' approximately 11:30 a.m. and the deflated transfer canal seal was detemined to be the l
l source of the leak at 10:30 p.m.
Air supply to the seal was restored shortly j
the.reaf ter and by 10:55 p.m. fuel pool water level had returned to normal.
Release to On-Site Pond and Radiological Consecuences Technical analyses determined that approximately 141,500 gallons of water leaked from the spent fuel pool during the period in which the transfer canal seal was deflated.
Approximately 17,000 gallons were recovered in the Unit I and II sumps, leaving some 124,500 unaccounted for. Undetermined quantities of water were retained in the Turbine Building Hot Machine Shop, l
the rail access to Unit II, the Unit II Nitrogen Storage Tank room, and other plant structures.
Some of the water eventually entered at least one j
site stom drain which drained to a swampy area to the northeast of the plant site behind the cooling towers.
Figure 1 is a GPC property plan for i
i t
FIGURE 1 1.
1 1
i i
't i
i i
i i
i
's l
w o
..i-s
.s is, l
c tg
"&*,[U....>.
..p. ~,.g~ ~
l ue..
/
. '\\
6i 1 -.
l s
."1,
.. ~ '
,'t 'U
- g. #.
1 i
w.
M</ Ji
- b. } v.-
I
/
U y
/
[j
..,f w.
ss
~
./
n t
- 1!
it 1:r.
'Z..:. Q r.
l j
s./
,1 x.b
.c
=
~
/n
% ~* %
- )
i
.M In
- 2~
L'I k_
j 3d7 w
U n
w Q,
f 4w=
i Lt
.i g
?,' /r g
i w-.l M
i THIS AREA SHOWN Ad
%w.c.'
Ir[ FIGURE 2
~T
~
F e
f
.t. I ii
- .w-.
e!
, L,.
m
- ?
/ k't
.I i j
-Lar**
+
- t:".
Y g
n-..
.q nu ;
a.a..,P
......,.. 1%.... -A E.*
n.
un.
2E!!!-
-4*.ie-- - -
m
,1 11 il
- lj il il *:
33 11 II IL 11 il geg is ss 3:
sa
$ k st
- IE A
l 1]
i.
=
g m
el
FIGURE 2
\\
2
=~.
p.,
s
,c c.
v
'). "-.['s
'g kI%
g
'%s 4
- .m I4
$ g x.,,,.',,,* '~ ] %
e.m
,/fw:l'h'~
-};
N~
~
I' li u
s
<y
,it
.t go_
,/ /
1
. C2
/.
ts I
f 9 Rm
. -1 m
1.. s. &' f.
I 1
=
9
- - \\ p x.s \\ l-i,-
rr
- ,d
- r...e
/
1 l
1
--l l
T...
,jl-
~'
x2. '
\\ ( / --
_ 1,-
\\,-
)
~
\\. h.k,_g,,4 N
g.'
se 9
i i
s
_v,__t g.,
t r
N l
l q
/.
s
/
s.w3.\\e,. -
t v-
'g
.. y o4 o.
v _o o
, - ~
s 0-.
l
- j. 's y
g,,,
?If:
--I J _T
\\
,c -
x\\..
==
=
s
' h'~., y,Q ?
ws
' \\\\
~*s.
J Il. < s\\
d//
'e, '
N,..\\
g\\
i II f
,x\\, l-: :: ::, % ~,,
l
,. 'e t
s 9-q.
l Il t,',
/
' \\}
an
/(~ $
W.D'n
.)
II l
fwf A.y ll
\\,.m
- y t
y w
], [
/f m
\\g dif [,ff I
l
%N\\ /' f l
caoncen sowan co. atunta a
's,
-/
O.
.n 4
/.,,,', m
(
}, [
m==*
"i s t
,f,
}3
_j'
\\
/,,;, v p
sowes t hatow wupsAn punt i
,\\T am EBE
\\ \\~,
I, k\\
,G s
w
/
/
s
[.../
I to Sot Is 80190 I
_~ M
[
i
-j h
j
' '-^
~ y_
a 3
\\
- m' m*
f4 l
\\
1 e
p
the Plant Hatch site.
Figure 2 shows the on-site pond area. The area shown in Figure 2 is indicated by the box in Figure 1.
1 GPC surveys of the stom drains in this area identified one (1) contaminated I
drain, identified at point 11 in Figure 2.
Water exiting this drain was observed to run approximately 100 yards along a shallow creek bed and then enter the pond at Point A.
Water flow within the pond was virtually non-i existent, and the activity was observed to slowly diffuse into the swamp, presumably with some of the activity settling out in sediment and vegetation.
j A small flow of less than 5 gallons per minute (gpm) was observed exiting
]
the pond at Point B.
i The initial contents of the 124,500 gallons of unrecovered pool water were
)
{
373 mill 1 Curies (mC1) of by-product material, primarily Cs-134 and Cs-137, l
with smaller quantities of Co-60, Mn-54 and Zn-65, and approximately 200 l
A substantial portion of the by-product activity l
was removed as the spilled water flowed over soil between plant buildings l
and site stom drains.
Additional activity was removed by silt inside the j
drainage system.
i Initial concentrations of radioactivity in undiluted spent fuel pool water l
were in excess of 50 times the Maximum Pemissable Concentrations (MPC) for 1
l water for unrest;1cted access.
At the stom drain outfall, concentrations were roughly
- equivalent to MPC levels.
Initial concentrations at the pond r
j inlet (Point A) were less than MPC levels, ranging up to 50% MPC.
After diffusion into pond water concentrations in the pond stabilized at 5-10%
of MPC levels. No activity was observed at Point 8.
Measurable activity was deposited along the creekbed leading from the stom drain outfall to the pond.
Radiation levels were observed to range from essentially background levels of 10 microrads per hour (pR/hr) to 500 pR/hr j
at contact.
GPC Mittaation and Assessment Actions i
j GPC health physics and chemistry (HP/ Chem) technicians were dispatched to j
the stom drain outfall area shortly after midnight on 4 December,1986.
Construction crews were also dispatched to the area to construct retaining i
I i
1
I j
dikes below the drain outfalls to pr; vent further contasination of the creek-bed.
Temporary dams were constructed inside storm drain feeder lines and the main storm drain to minimize further water entry into the spill area.
By the time EPD personnel arrived at the scene, GPC HP/ Chem personnel had established access and egress control to the area. Areas of known contamina-tion were roped and posted, and overboots and dosimetry were required for entry to the general area.
On the af ternoon of 4 December, 1986, GPC workerews identified the small l
outflow from the pond at Point B.
Although later sampling indicated that none of the released radioactivity had reached that Point, GPC personnel were dispatched to the area to construct a dike to prevent any possible transport of activity to the Altamaha River.
Workmen carried necessary
}
equipment for construction of the dike, as only foot access to the area i
was available.
]
Beginning early on 4 December,1986, GPC HP/ Chem technicians collected hourly wate'r samples at seven (7) locations.
Samples of pond water were collected j
and direct radiation measurements in the pond were perfomed by HP/ Chem technicians using a duck boat.
Periodic boat runs to collect water samples
{
were performed on the Altamaha River.
Samples were analyzed using radiation detection equipment at Plant Hatch and results of analyses were available 4
l in the Technical Support Center (TSC) on-site.
i On the af ternoon of 5 December, 1986, GPC personnel collected core samples from the creekbed and performed a walk-over survey of the area to determine the amount of activity contained in the area and the amount of soil removal necessary.
l Assessment activities were continuing up through the writing of this report I
j to detemine the disposition of the activity involved in the spill. Approxi-I mately 88% of the spilled activity has been accounted for, and is known i
not to have entered the swamp.
Measurements in the swamp indicate that only 13% of the released activity enterred the swamp, and approximately 7% of the activity reached the creekbed.
i As of the writing of this report, the disposition of the estimated 373 mci
i of by-product activity leaving the spent fuel pool is as follows:
1 Nitrogen Storage Tank area (soil) 205 mci Sludge removed from stonn drain 84 mci Soil / vegetation removed from the creekbed 12 mci Soil / vegetation remaining in creekbed 14 mC1 Removed from treated water 12 mci i
Routine liquid radwaste 2 mci Remaining in swamp 0.5 mci 329.5 mC1 a
Investigations as to the disposition of the roughly 43 mci of activity unaccounted for have focused on the following areas:
deeper soil in the Nitrogen Storage Tank room, any activity which may remain in the seismic i
gap between the Unit I and Unit !! Reactor Buildings, contaminated on-site asphalt, and bags of ion exchange resin used to filter water in the stonn drain.
It should be noted that at previous spills of a similar nature at other nuclear facilities, accounting for more than 25% of released activity is extremely uncommon.
The high degree (88%) of by-product material account-ability obtained by GPC during this incident is remarkable.
Due to the analytical uncertainties inherent in radiological measurements, it is entirely possible that all spilled material has been accounted for.
Of the, estimated 200 mci of tritium (H-3) in the pool water, an estimated 27 mci are contained within the pond.
1 P
J 9
i l
i
DNR/EPD Actions The Environmental Radiation Program (Rad Program) of the Georgia Department of Natural Resources. Environmental Protection Division (DNR/EPD) was notified of the release at 8:00 a.m. on December 4,1986 by GEMA.
The Program Manager (Mr. Hardeman) was in Dothan, Alabama for a rteting with the Federal Emergency Management Agency (FEMA) to receive the initial FEMA evaluation of the i
radiological emergency exercise held the previous day (December 3, 1986) at the Joseph M. Farley Nuclear Plant.
In the Program Manager's absence, the Branch Chief. Program Coordination Branch (Mr. Setser), dispatched an Environmental Specialist (Mr. Schreiber) from the Rad Program to Plant Hatch
{
to collect confinnatory samples.
Mr. Schreiber left the Atlanta office i
at 10:00 a.m.
I l
The Program Manager (Mr. Hardeman) was advised of the incident in Dothan, l
Alabama by representatives from the Georgia Emergency Management Agency l
(GEMA) who had received notification earlier that morning.
After conferring I
with Mr. Setser in Atlanta and GPC representatives at Plant Hatch (Mr.
1 Zavadoski and Mr. Ewald), Mr. Hardeman advised GEMA that he would be unable l
l to attend the critique of the exercise, and at 10:30 a.m. departed for Plant Hatch.
[
The other two members of the Rad Program staff, an Environmental Specialist j
(Mr. Blackman) and a Laboratory Scientist (Mr. Gary) remained in Atlanta at the Environmental Radiation Laboratory at Georgia Tech and made necessary
{
preparations to receive and analyze samples as necessary throughout the night.
l Mr. Schreiber arrived at Plant Hatch c.t 1:12 p.m., and after being granted security access proceeded to the area on the release at 3:00 p.m., accompanied j
by a DNR Law Enforcement ranger (Mr. McDaniel).
Mr. Hardeman arrived at Plant Hatch at 2:35 p.m., and proceeded to the Technical Support Center (TSC) for a status briefing from Mr. Zavadoski.
After reviewing available monitoring data and GPC actions to contain the released material, at 3:45 i
p.m. Mr. Hardeman proceeded to the Visitors Center to confer with Mr. Ewald, who was now serving in the capacity of Company Spokesman.
l l
Upon his arrival at the Visitors Center, Mr. Hardeman called Mr. Setser j
in Atlanta for a status update, and was advised that the helicopter scheduled l
l
l to arrive at Plant Hatch at 4:00 p.m. to transport samples to Atlanta had -
been delayed.
By this time, print and electronic media representatives had assembled at the Visitors Center, and Mr. Hardeman requested and received authorization from Mr. Setser to provide information regarding EPD activities related to the incident, assessments of GPC activities, and assessments as to the severity of the incident.
Due to media interest, Mr. Hardeman was unable to imediately proceed to the incident scene as planned.
Mr. Hardeman had responded to the incident in his personal vehicle, and did not have access to a DNR radio to contact Mr. Schreiber or Mr. McDaniel.
Upon the arrival of the DNR helicopter at 5:20 p.m., Mr. Hardeman requested the pilot to take him up for a fly-over of the incident scene.
Mr. Hardeman l
attempted to contact Mr. Schreiber by radio from the helicopter and was unable to establish contact.
However, he did contact. Mr. McDaniel and requested him to advise Mr. Schreiber that the ' helicopter had arrived and was ready to transport samples to Atlanta.
Mr. Hardeman returned with the pilot to the Visitors Center at 5:25 p.m.
At 5:35 p.m., Mr. Schreiber arrived at the Plant Hatch Visitors Center with seven (7) 1-11ter water samples collected in conjunction with GPC health physics personnel.
After Mr.
Schreiber surveyed the samples and determined that there would be no hazard to the pilot, the samples were placed in the helicopter for transport, and at 5:40 p.m.,
the helicopter departed Plant Hatch for the Capitol Hill helipad.
After the helicopter departed, Mr. Hardeman and Mr. Schreiber contacted Mr. Blackman at the ERL and advised him of the estimated time of arrival (ETA) of the helicopter, and the priority in which the samples were to be analyzed.
Mr. Hardeman then contacted Mr. Setser and advised him of the I
status of the response.
In the course of this discussion, requirements for additional sampling were identified.
It was agreed that Mr. Hardeman and Mr. Schreiber would remain in the area overnight, with Mr. Schreiber performing the additional sampling on the morning of December 4, with the l
assistance of Mr. McDaniel.
Af ter securing accomodations for the night, Mr. Schreiber departed Plant Hatch at 6:30 p.m.
At 7:00 p.m., the DNR helicopter arrived in Atlanta at the Capitol Hill helipad, and samples were transferred to Mr. Blackman, who took them to the ERL. Sample preparation and analysis began at the ERL at 7:30 p.m.
Mr. Hardeman, escorted by Mr. Ecald, proceeded back to the TSC before departing Plant Hatch.
After receiving briefings from Mr. Tsakeres and Mr. Kirkley of GPC, and being advised that Mr. Rogers would be the shif t replacement for Mr. Zavadoski during the night, Mr. Hardeman departed Plant Hatch at 8:25 p.m.
At 9:00 p.m., Mr. Hardeman contacted Mr. Blackman from his hotel room in Vidalia, Georgia.
Mr. Blackman reported analyses on the first three (3) samples.
The most important of these samples was the one taken at Point B on Figure 1, the only known outflow from the pond to the Altamaha River.
No activity was detected in this sample.
The other two (2) samples were from the stonn drain outfall and a point in the creek leading to the pond.
Both of these samples indicated the presence of Cs-134 and Cs-137, and the sample from the drain outfall also indicated the presence of Co-60.
The radioactive material concentrations in both samples were substantially less than MPC levels. During this conversation, Mr. Blackman advised Mr.
Hardeman i
of requests for this data from Atlanta-based electronic media outlets.
At 9:20 Mr. Hardeman called Mr. Rogers at Plant Hatch to compare sample results. EPD and GPC results were in excellent agreement, and both indicated that none of the released material was entering the Altamaha River, con-sistent with the GPC analysis of the situation.
Between 9:40 p.m. and 10:10 p.m., Mr. Hardeman contacted both EPD management and Atlanta media to advise them of the results of EPD sampling and their confirmation of the GPC assess-ment of the incident.
At 11:45 p.m., Mr. Blackman called Mr. Hardeman and advised him of analysis i
results of the remaining four (4) samples.
He also advised that he and Mr. Gary were in the process of closing the ERL for the night.
At 12:05 a.m. on December 5,1986 Mr. Hardeman again contacted Mr. Rogers at Plant Hatch to discuss the latest analyses.
As before, EPD values were in good agreement with GPC data and further confirmed the GPC assessment of the incident.
1 At 7:30 a.m. on December 5, 1986, Mr. Hardeman and Mr. Schreiber arrived i
at the Visitors Center.
Mr. Schreiber had contacted Mr. McDaniel while en route to Plant Hatch and requested his assistance in sample collection.
Mr. McDaniel arrived at the Visitors Center at 8:00 a.m. and at 8:15 a.m.
1 l
, _.. _. _.. - - - - -. _ ~
Mr. Schreiber and Mr. 'McDaniel departed to collect 'the samples, af ter which 4
Mr. Schreiber would return to Atlanta, transporting the samples to the ERL.
Mr. Hardeman contacted Mr. Setser in Atlanta and was advised that he needed to contact Mr. Gloersen of the U.S.
Nuclear Regulatory Comission (NRC) regarding recovery actions.
At 9:00 a.m., Mr. Hardeman met Mr. Gloersen at GPC Security and they proceeded
(
to the spill site.
At 9:30 a.m., Mr. Hardeman and Mr. Gloersen accompanied l
GPC HP/ Chem staff as they performed their hourly survey of the spill area.
Mr. Hardeman observed a large dike beneath the contaminated stonn drain l
outfall (11 on Figure 2) and at two (2) additional outfalls earlier suspected of being contaminated, but later detemined to be clean.
Mr. Hardeman also observed GPC personnel pumping water from the area beneath the outfall and
{
from the stom drain to a nearby water truck.
GPC personnel had also packed i
sand and bags of ion-exchange resin into and beneath the storm drain' to trap radioactivity before reached the creek or the pond.
At 10:00 a.m.,
Mr. Hardeman and Mr. Gloersen reached the only known outflow from the pond
{
(Point 8 on Figure 1) and observed two (2) dikes across the outflow.
No j
outward flow from the pond towards the river was observed.
GPC personnel were taking soil from two (2) nearby borrow pits and placing it in bags
)
which were then used to augment the dike closest to the river.
i At 10:10 a.m., Mr. Hardeman and Mr. Gloersen entered the controlled area surrounding the small creek downstream of the stonn drain outfall.
While GPC personnel collected water samples, direct radiation measurements ranging j
from 0.5 millirem per hour (mR/hr) in the creekbed near the outfall to '0.04 mR/hr where the creek entered the pond were observed.
At 10:25 a.m., Mr.
Hardeman and Mr. Gloersen left the area after being surveyed for contamination and found clean.
Mr. Hardeman discussed split sampling requirements with Mr. Link of GPC, who agreed to have GPC personnel collect four (4) samples once per day for EPD as long as daily (or more frequent) sample collections continued.
After exiting the spill scene. Mr. Hardeman and Mr. Gloersen briefly discussed j
the situation with Mr. Beckham, Vice President of GPC.
Mr. Beckham was l
advised by both Mr. Gloersen and Mr. Hardeman that GPC containment and j
assessment actions appeared adequate.
While leaving the area, Mr. Beckham i
I
. _ = - - - -
s was observed escorting Mr. O'Reilly, Senior Vice President of GPC, and Mr.
l Miller, President of GPC, into the area.
i l
i l
At 11:15 a.m., Mr. Hardeman and Mr. Gloersen arrived at the Visitors Centar.
At this point, Mr. Hardeman responded to media inquiries and Mr.
Gloersen l
contacted other NRC personnel at the plant.
Within the hour, Mr.
Gloersen l
returned to the Plant.
At 12:15. Mr. Hardeman and Mr. Ewald discussed plans j
[
and alternatives for short-tem cleanup and long-tem monitoring.
After j
]
briefly discussing the incident with Mr. Miller and Mr.
O'Reilly, Mr.
Hardeman and Mr. Ewald returned to the TSC.
There, they met with personnel from GPC Environmental Affairs and Mr. Gloersen to discuss short-tem and 4
long-tem monitoring requirements.
It was decided that two (2) composite j
water samplers would be installed as soon as possible; one at the outflow l
from the pond (Point 8 on Figure 1) and one in the Altamaha River imediately j
downstream of the pond (Point C on Figure 2).
GPC will also propose a j
sampling program for sediment and vegetation within the pond.
It should j
be noted that no suitable vegetation is currently available.
I i
After this meeting Mr. Hardeman and Mr. Gloersen met privately to discuss j
the incident and review GPC proposals for cleanup and monitoring.
Both agreed that GPC proposed activities were adequate. After receiving an update l
briefing from Mr. Kirkley of GPC, Mr. Hardeman departed Plant Hatch at 4:30 p.m.
i i
At 8:30 a.m. on December 6, 1986, Mr. Hardeman contacted Mr. Kirkley at I
i the Plant Hatch TSC and received a status update.
He also made arrangements j
to have a radiological sumary report being prepared by GPC telecopied to j
him in Atlanta upon its completion.
At 10:00 a.m., Mr. Hardeman cor,tacted l
Mr. Ewald at the TSC and received a further update.
At 1:15 p.m., Mr. Herz of GPC called Mr. Hardeman and requested concurrence on a press release f
i GPC in Atlanta was preparing.
In discussions on this release, Mr. Tavadoski advised that initial soil removal in the creekbed had begun, concentrating on." hot spots" with activity great enough to cause direct radiation levels in excess of 0.5 mR/hr.
Mr. Hardeman advised GPC that he could not concur with this release until he had more infomation concerning the removal of i
contaminated sofi.
Mr. Hardeman contacted Mr. Zavadoski at 3:00 p.m. and was infomed that soil removal was continuing slowly.
At 5:30 p.m., Mr.
l Altman of GPC called Mr. Hardeman in reference to the earlier draft press i
f
[
/
l*
release.
He indicated that it stt11 had one final round of approvals to I
receive, and that it would probably be supplied to the wire services on j
i j
the afternoon of Sunday December 7,1986.
At 7:00 p.m., Mr. Ewald called to advise Mr. Hardeman that the two (2) composite samplers had been installed fl and that EPO would receive its daily composites probably every other day beginning Monday, December 8, 1986.
Mr. Ewald also advised that removal I
j~
of contaminated soil would continue on Sunday, that the creekbed would be re-surveyed after removal of all spots greater than 0.5 mR/hr, and a decision made as to future activities after the re-survey.
Water recovery was
{
continuing, but exact figures on volume and activity recovered were currently unavailable, but would probably be available on Sunday.
l At 1:00 p.m., on Sunday, 7 December,1986. Mr. Altman contacted Mr. Hardeman l
to again discuss the press release.
At 3:45 p.m., Mr. Ewald called Mr.
r Hardeman to discuss the status of cleanup activities.
At 4:05 p.m., Mr.
F j
Altman again called to discuss the press release, and advised Mr. Hardeman
{
that GPC personnel at Plant Hatch had requested a de, lay in the issuance of the release.
This press release had not been issued as of the writing
[
of this report.
I 1
j On Monday, 8 December,1986. Mr. Hardeman returned to Plant Hatch, arriving at the spill site at 1:00 p.m.
Af ter having received a camera pass Mr.
[
Hardeman proceeded to re-survey the site and document containment and cleanup i
l activities.
'Mr. Hardeman observed soil and vegetation removal activities.
(
4 l
At approximately 2:00 p.m., Mr. Hardeman met Mr. Ewald while exiting the l
a rea.
Shortly thereaf ter, Mr. 0111nger and Mr. Maulsby, both of GPC, arrived j
}
at the spill scene with a third !$C0 water sampler.
Mr.
Hardeman observed I
GPC personnel setting up this !$C0 sampler to collect daily composites for both GPC and EPO at the inflow to the swamp (Point A).
After exiting the area, Mr. Hardeman, Mr. Ewald, Mr. Zavadoski and Mr. Nix (GPC Plant Manager l
at Hatch) discussed restoration of essentially clean drainage flow to the stom drain system.
The consensus of the group was that restoration of the small (approximately 20 gpm) drainage flow would not alter the j
radiological conditions in the area and would not hamper further cleanup l
activities. Mr. Hardeman, accompanied by Mr. Ewald, then reviewed the earlier j
walk-over direct radiation survey of the area, and performed a confirmation i
walk-over. Measurements were in good agreement with GPC measurements.
i I
i I
_ _ =
l' At approximately 5:00 p.m. on 8 December, 1986, Mr. Hardeman observed GPC personnel perforining activities related to restoration of drainage flow.
under close health physics supervision, bags of ion exchange medium were removed from two (2) locations near the end of the storin drain.
Pumping from the main storm drain was discontinued, leading to a flow of less than 5 gpm from the drain.
Later, sandbags were removed from a feeder line to the drain and pumping at that location was discontinued, leading to a slight increase in drainage flow. At approximately 6:15 p.m., Mr.
Hardeman departed the spill scene.
1 Mr. Hardeman returned to the spill scene at 7:30 a.m. on 9 December,1986.
After briefly observing continuing cleanup activities and discussing the situation with GPC personnel, Mr. Hardeman returned to the Administration 4
j Building to begin the process of obtaining an access badge for Plant Hatch to facilitate future monitoring of the area.
At approximately 12:30 p.m.
)
Mr. Hardeman returned to the spill scene and observed gravel operations i
continuing in the creekbed.
A brief walk-over survey of the area at 1:45 p.m.
showed no areas with direct radiation levels greater.than 50 pR/hr, with an average radiation level of approximately 25 pR/hr, roughly twice j
the average background radiation level in the area.
At 2:30 p.m., Mr.
Hardeman received approximately forty (40) samples collected for EPO by GPC to transport them to Atlanta.
After briefly discussing the situation i
with a local reporter, Mr. Hardeman departed the site. Samples were delivered to the ERL at'8:00 a.m. on 10 December,1986.
1 1
j l
i
\\
\\
l l
i
t Short-Tem Cleanup i
l Cleanup of the spill scene by GPC began as soon as GPC, the NRC and EPD were assured that the spilled activity had been adequately contained.
i Short-tem cleanup activities conducted by GPC included removal and treatment of contaminated water from the stors drain system, removal of contaminated soil and vegetation from the creekbed, and removal of contaminated silt l
l from the stream drain system.
i j
Recovery of contaminated water began on the afternoon of 4 December,1986.
l Sags of ion exchange resin were placed inside the storm drain system to l
remove some of the contained cesium prior to collection.
Collecte'd water t
j was pumped into tanker trucks and transported to the Rad Waste Handling f
Building.
There, the water was mechanically filtered and passed through
{
ion exchange media to remove suspended solids and most of the remaining l
activity. Recovered water was sampled before and after treatment te determine the amount of activity removed during treatment.
After treatment, recovered 5
i water was introduced into the liquid radweste systems in the plant, and t
a l
subsequently released to the Altamaha River in controlled radweste discharges.
}
l As of 10 December, 1986, approximately 71,000 gallons of water had been l
recovered and treated.
An estimated 12 mci of activity, primarily Cs-134 i
I and Cs-137, were recovered during treatment, and an estimated 2 mci were introduced into plant radweste systems and released in routine controlled batch releases.
j GPC removal of contaminated soil and vegetation began on 6 December,1986.
A survey the previous day indicated several areas with direct radiation l
levels at or above 500 pR/hr.
After initial removal of these " hot spots",
j maximum radiation levels were reduced to 190 pR/hr as measured by GPC and j
EPD walk-over surveys of 8 December,1986.
Further removals of contaminated
]
soil and vegetation reduced maximum radiation levels to 45-50 pR/hr, as measured by GPC and EPD surveys of 9 December,1986.
A total of 300 cubic feet (ft8) of contaminated soil and vegetation, containing 12 mci of j
by-product activity, was removed from the creekbed area, leaving roughly I
14 mC1 of by-product activity distributed somewhat uniformly in the area.
l l
To prevent further contamination of the spill area, GPC personnel began removal of contaminated silt from the stom drain system.
Approximately i
. i
200 f t8 of silt, containing 84 mCf of by-product activity, were removed from the storm drain system.
On 5 December,1986, GPC, NRC and EPD staff discussed alternatives for cleanup l
of the swamp itself.
Assessments indicated that a total of approximately 4
of ' ritium were present in the 0.5 mci of by-product activity and 27 mci t
swamp, and that further releases into the swamp were unlikely.
After reviewing all available
- data, all parties agreed that the adverse environmental impacts to the swamp which would result from cleanup activities 1
were unwarranted by the amounts and concentrations of material present.
Instead,- it was determined that the most appropriate course of action would be to allow the material to remain in the swamp, and to monitor the swamp and its outfall to the Altamaha River.
Short-term monitoring consists of three (3) composite water samplers at Points A, 8 and C in Figure 2.
Lona-Tem Monitoring Discussions between GPC, NRC and EPD regarding the need for long-term j
monitoring of the spill area began on 4 December, 1986.
On 5 December, 1986, Mr. Hardeman met with Mr. Gloersen (NRC) and Mr. Ewald to discuss monitoring.
In sumary, GPC had proposed to the NRC that monitoring in the area be in the form of an augmentation to the routine GPC environmental moni toring program at Plant Hatch.
NRC approved the proposal, and EPD concurred, p,roviding that detailed short-term monitoring to assess the j
effectiveness of cleanup activities continue until temination is agreed l
upon by NRC and EPD, that GPC provide split samples to EPD for analysis, i
and that EPD be provided routine unescorted access to the spill area for the purposes of future monitoring.
It was agreed that Mr. Hardeman obtaining an access badge for Plant Hatch would simplify future access to the area.
The discussions on long-tem monitoring revolved around media, number of l
samples, location and frequency.
The sample media agreed upon were:
pond water, water from the Altamaha River immediately downstream of the pond, j
pon'd sediment and pond vegetation.
Pond and river water would be sampled l
daily at three (3) locations (A, B, and C on Figure 2), with the sample frequency being reduced to weekly within 1-2 weeks following completion l
of cleanup activities.
The number of sediment and vegetation sampling
}
locations and sampling frequencies were left undetermined.
In the next l
4
~~,.---r-,,.,w,
,,,,y..--~..-.----,.---,-......,,..-,--,,,-m.-m.
.,--,-..-..-..-v,-----
- - -.. - -. +, - -
-~m-,---,..m--
- - -. -. - - -. - ~,
week, GPC will be developing its augmented monitoring plan for the area, in conjunction with EPD, and will submit the plan to NRC for approval.
The EPD Environmental Radiation Program. plans to monitor this area on a periodic basis to be detemined.
Measurements in addition to those performed in cooperation with GPC may include periodic walk-over direct radiation
- surveys, in-situ gansna spectroscopy, And "idditional collections of environmental samples such as fish.
GPC officials have assured that routine unescorted access to this area of the plant. site will pose no prob,*,em.
It is expected that af ter two (2) quarters of ' rionitoring at and in the l
vicinity of the spill site, GPC and EPO officiais will perform a formal I
assessment of all monitoring data acquired, and/ will make reconsnendations regarding the necessity and/or advisability of further monitoring in the
)
a rea.
i j
4 1
Findings (1) On or about 3 December, 1986, approximately 141,500 gallons of water leaked from the spent fuel storage pool at the Edwin I. Hatch Nuclear Plant (PlantHatch).
(2) Approximately 17,000 gallons of pool water were retained within Plant Hatch and recovered.
(3) The estimated activity in the pool water released was 373 mci of by-product material (Cs-137, Cs-134, Zn-65, Co-60, and Mn-54) and approximately 200 mci of tritium (H-3), all licensed by the U.S. Nuclear Regulatory Comission (NRC).
(4) Georgia Power Company (GPC) perfonned actions necessary to assess and mitigate the spill.
(5) Slightly elevated direct radiation levels and water radioactivity concentrations were observed in the swampy cyprus pond a rea and in the wooded area below the storm drain outfall.
(6) On 9
- December, 1986, maximum direct radiation levels and water concentrations in the spill area were well below those levels and/or concentrations requiring restricted access.
(7) Approximately 0.5 mC1 of by product material and 27 mci of tritium remain in the swampy cyprus pond.
(8) Approximately 88% of the estimated quantity of by-product material released has been accounted for and recovered by GPC.
(9) GPC has installed three (3) composite water samplers on the pond and/or the Altamaha River.
To date, there has been no indication of any material released entering the Altamaha River.
Split samples are being provided to EPD.
..c Conclusions (1) Georgia Power Company (GPC) actions to assess, mitigate and recover from the spill of 3 December,1986 were prompt and effective.
(2) No radioactivity has entered the Altamaha River as a direct result of this spill.
(3) The remaining activity at the spill scene, including the radioactivity contained in water within the swamp, poses no danger to nearby residents, downstream water users (if any), consumers of fish from the Altamaha River, or wildlife.
(4) No reason e.tists for restricted access to the spill area.
- However, Federal and state regulations require GPC to post the area as a
" Radioactive Materials Area" due to the presence of residual by-product material.
(5) Approximately 14 mci of by-product activity remains in the soil and vegetation in the creekbed. Approximately 0.5 mci of by-product activity and 27 mci of tritium remain in the swamp.
These activity levels lead to a maximum direct radiation level of 0.5 mrem /hr in the creekbed and a radioactive material concentration of approximately 5% of the maximum permissable concentration (MPC) in the swamp.
e 6,
O Reconnendations (1) Enhanced monitoring in and surrounding the spill area, with emphasis on direct radiation measurements and sampling of pond water, river water, pond sediment, pond vegetation, and fish from the Altamaha River, is recorsnended for the next 6 months as a public assurance measure.
Monitoring activities should be performed by GPC in conjunction with EPD, with independent confirmatory measurements and sampling by EPD.
A joint assessment of acquired monitoring data by GPC and EPD is recommended at the end of the 6 month period, to determine the need and/or advisability of further monitoring activities.
'l 9
e i
'/o eend 4 a:,J ht w
w M
a s.
o A
N m
4
/2 l c c
d Xl ti (O
T
(
3 l ""2 n
yu a
I}
1 S
N of
'4 Q
[3 k v
4 s
1 S
i S
ol g
w g
- d...f E
w.
5' -
w"0-N og sP m
n,5 ar 4(
o -;
i
,{
u a
N
...ninin.n p nia E Od t
V ppm;p E
a e mr
!r,-
o A
4.'y4'!;
r
%,, Fd.i g
M.
tit r
t d
n
+ <z N
,s a
N
-8 T
3 E
P 1
N m
E c
d v
6'.
T b
- + -
p Pd LJ O
l w
3 T4&
N
< a/ 3 n e
o
- M k T-3-
rz r-Y e.
?.
g g b s
a.Qyx =
..d@
PGT gcx
,e
~
)
~
1
%l te
_7
{}4 tM m
p
,,.Py_Ai
=
3; _-
s
.3 J_,
Y k
dh k
~s'; %[r 9[,
di t
p,j; Xms w%., __
., : s g
.,9 s
=
I p
'o.m :
O
'N_gg-i
'f15* 7 3 9) 4.
Y]
Ab/ Dik L b@Mt.-1M
'G
)
f pogy - S g-76 d/3
17: 12 BECHTEL GAITHERSBURG/ HATCH PROJECT P.02
..a L.j C.) F/9ys 3 Q
i 4
CALCULATION SHEET x
e= = =
.wuin
,CSIC.
CALC.SC.
D. SC.
DEET NO.
wron om cmoun oAn 1
- .i 4
e
, p.
N. o. [,
/
- I l
Jy _i
_a..
t a
- l.,. _
T.
...., ipp i I
s I
4 t
.s
.e, A.
.- B e a
i l....
n --
>... ).
)..
I
..-l i
..1j... :.
nor e
s j
.. g l.
- ~,e.i
.e< nt.enut e
1.1.__.
..:.... g}...
..l
. g :; <....
e s
i i
u.
1
.i....i...
o.
...c' i
y,..
J.
Ws l
l
. s u. l.
to 1.
k uusfI..
users.
l v
uude Asg a rot f used4 l
.a uusf 1
.syws
[.
.sg s 1.. '.
/
ss.W:Iri - sienuws s
4
..L w s d Pi.. t
- 1-Soce 6 :l l ! "j...._l i. f !.1.1
!!,"'*~f l.aF j'.l.
i i. l 4k.
,- i t
4 g.,
. n,..
~. v. - n
.o 1_
=
i.
q..,
ii-7t-
. i it t !
i e su m- - -- - - - - -,j
.pu'i-
. o g ! i.
L_.__u.u!jrii.
n i
., l i.
.__ w;.i.,,-, iwir't..
u u
n n t wir.
_u u,u sic.. _._
.:s c
_i.
.. n.. i.u.. s o
3 ao l
...g tpg..
.ru att NK :.-
81 i
.I '.j i
8 g n 9.,...
as i
i i
.p.. :
as J pJr.M.'..
. L.j'.
..i. j..; _.
. 4...
i, l.,j
=
i
- i...
.i.
.... ]...
\\..
. $ h %.N..
N
. i..e 4:.g
....,. ' "...; : ;,.,.. 7. ; Y,.. n 87
- l*
I J 71
! J?
l.
.q. -.p
'. 6
..n
.). J.
- . D - i.
=
i i....,...
E 8
4..' h.
'9*4 O...
l
..l..._. ;[..
l
+
7
- g..
l 3.,
i,
.. SENT. TEI ECDPY j-
.'.:%j I
I
> g gg. -
.r..
.....Q.. d.
f, i
.i l
. 4_. l l
at r
.n.
i.
.q c)
Fag-71-76
..i..!...
.......i. !
ii
,P
.c/3 l
i i
o. i....i m
l
- . ' : '. /.M : VE. EF TL"E:0 3
- :;."1:Lh'/ PTE_,TPEATME!jT L:M: TING CONDITION FOR OPERATION 3.25.1.3 The liquid radwaste treatment system, as described in the ODCM, shall be used to reduce the radioactive materials in l
.:qu:d wastes pr:or to their d2scharge when the projected doser due to the laqu:d effluent per Unst fror the site (fagure 3.35-1) when projected over the calendar quarter would exceed i
C.18 mrem to the total body or O.62 mrem to any organ.
APPLICABILITY At all times.
ACTION a.
With radioactive liquid waste being discharged without treatment and in excess of the above limits, within 30 days, prepare and submit to the Commission, pursuant to Specification 6.9.2, a Special Report that includes the following information:
1.
Identification of the inoperable equipment or subsystems and the reason for inoperability 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status 3.
Summary description of action (s) taken to prevent a recurrence.
b.
When the ACTICN statement or other requirements of this LCO cannot be met, steps need not be taken to change the operational Mode of the Unit.
Entry into an Operational Mode or other specified condition may be made if, as a minimum, the requirements of the ACTION statement are satisfied.
SURVEILLANCE REQUIREMENTS 4.15.1.3.1 Doses due to liquid releases shall be projected monthly in accordance with the ODCM, during-periods in which discharge of untreated liquid effluent containing radioactive materials to UNRESTRICTED AREAS occurs or is expected to occur.
e-e p3g-29-71.
6/y 3.15-7 l
d.-
.4
V.i. a%,-.
iQ,lr &.#.. 3.M..
-t : ;
. '.. '. G.
- C....% Ws
,,, 's.., t..
.s f.,.,
- . d, "..
W'.
- d. '
S. M.i t
A
.S.
4
.. e..:;.J... i...n,.
- c..,.
- s.,.
..y
...y v....s.
9
.l. lMM_
. ndeng2@on BSud. % _..~_....____ _._.
~..
p%. K
- gj,, x 3
. y. p.w.4.,.
., m...
~.
n +.
v w.w.
.c..
&'Cg."~~ pp,_._ QQQ.L R L...
_, z.
i
. s..
-u
, c
-$c # [bAmOW to_m.
TiAebb1nWI._ Slog _.76' Essa _R. _ot 4'.Y'.kf:., _t.W. i ;:beh.v.,_.."@" '
M0' g <.
w;.
.f,,,.;.f,
.g
..,. s.
p.
's
..i.
l
.;...J
[h5h'd bir's@hh.k'2b bYbN2.1
'NN.kk i '.fi '
%y%.94 O.
4frr%%...#
.. 51.'? % n' M..-.
.f - ' ' -
N
~
4 -F '
3'
?O x
Y
-r.b. G b. M "." 4 ' 6 '
1:-
'.Q.
,$ N hPbhS '.Oh..h f:.Y: N?
~~
,a.<.
- ...,. p.
,... e.
.:,... n. n,y,:.,..
u
-,.,..., a..
3
......s.
. e.
r..
8
. m.., -
j _
(*
- .,%.w +.,- a :..<
n_-
.p _.
........n.9,,.-
p-
.c.n. =..
..7 a
._ _.~.
_.... y.
n t.~.. c.
. v
,y,, %
h.
- m
.v.g T. ~.<.g;w g.e.
~
.,. c - _
~~
r J
....-4
..., m &., ;,. /......
4v. O J
c,..
.p..
1.>
TMj..,. M...
-:- x w. ~
s ; w'J t.,:*
m,.
2 J.
- 7..
P,,.:.&a. -
e..1
,%4 a.,d..,h..n,h.*
~.
4fe 4EVO-
' C.
.. ~
..~.g :-
4 <e -
vh;'N.. A.V Q:L..' ;t.~ $ g:. r.., Q. ;?t v
y@.; k.
~
2-;, -
~ % s'
- '^9%f '
- .i.i~k._ : ?'",
~ y ~"~'~, [.
~; *
' ~ '
+... W, ?...-11'u.-J,.c $qs. W.:<
Q.4
., n.
M. :. u.
~
~~
. nre.n,:. a; '.:.._,",.
.r.:...d..
..6s %y..
ne
+rf >* s.. :y :. g.
.g.
v.
p.:.:... y w
- ..t '- hs..az, ;m..
. ~ c.,,.
pg.
., )
..,.;*,g..... 2...-
~...
+
, re;
- *:;I ' ht:. n n.? " y
" ,'+, v,k
- y"i. ' 3s,y*
~...
-?
a s,.,g..
~.v.. $... m. 7..
j w..i r Y.
~&.
- .s.',
f'$b.f $h,g., w.i, h g f. h b h,
. 4..
qhh5,,?.;*
'{?.
i.
a.
h.h$$.$.Sh$h$hk,??$$hhk'hhh.W}k.k$
7tgWP.L W e rgygeggggg$4. g.g--~
~ {..-
M.,
?.
. a.
{ p
'ul.,.
a.ap*.' ;3-l, a
.. ~.......
,,a._
~'
f'b] N - $l- ]l.
jt
.wg. e
'. a. '
- 7.
hk M b b b k k..' N.! 5 N W 5 s ':r [.
- 4d'.k..$?E
~
n WhillaintFRMMMMMMMderQ
R k,1 W w.n.N We v y.. ~... nQ '.
' :c!. 3." : m^ ".
1
~..
t.y: m. -
.gu y
s m p<24. 4n
.a s s.mv.
.... n; "
. ~.
~}.
r n.
1 9 e n $..e.o.m..
,W.s... -9 6 6 ',/k O C L -
es
.dRQ,hW, j
- l."
... r.,..
-.,,,.. e,.
pdy.isu;g,,. w,.c 1.: : r ur. : g?..n% m; +'. :-
=
e-
?
2av#JDsdappw p *.Measchstg. :44P0-d E...
4 3
t'en.admmoq, Fatus
._.LN_.n. o
+
. Y. ? k. M & d ) #.'2 hh...W....., W
{
4lml mmd.lEM@f4%
e, -c
,..e::Mistsgn. c
~#..
r 4
5 E 2YO YI q.y. #4
.f.
e yq
~'
~ -
..cy q
g
- w
.., I 1.: : :. #4.-#.bW I l 1..VYh R
10A @ !
r
)i.
.h I
h hh:,
Cf.h' %
l I-U _i 9-h k J 22iW1B h%WM tifGBREM9GHW3"T i!WMENMWN2M MM tWM 1 /.t f'.h h Y,Y h
hk
^
.k.[
y{h, bif,'. k.)
.?[%fj$,%'l..
a' M t w&&... e,ST..'. lQ~QiM.CGW'Cy1efos.% ~54 yf~ &nt.Zv46+ font).o-foO T
Gd
~
a s
c, x _.a -
f.
.-% e :W v_9 9cM:p-D,.. :'n ~ mtpOm w o m ; p %.7. a p-~. v.
u.,
W
.v~4
.e ".
~ %..
.',.
- e ; 4.. 4... - _..;.'
.s ~.
A. ^ n.u...e,, $.
n.
...a.,
a:-
s.
.r
,%,., W. W g-~ f. Q4I l. --
r o
...?-
A..'..
Wc e =-
e
'x
..z se...
~
-~ n.
.:Ae.
's) _%., r.
/.4
=r
', e
._bl.
=
.. ' Q. *.O
,.., $' 0., e.\\, *k..
-. 'a. - ~. ;r...
... rf. u.;
,s
.' g R,
- \\ *.
,__'k,e _e.
..' ~
e 7,.,v.g.;m
,. _ y _ b_,.,.. u,. j..:.q*yL,_,c.,., -
. v.:. '.-
- . g._ _,6pp.,.....
~
--w...
I nMgeswe.cyg'.W+agw M+
p*,
..,- '.. 'c p..g
..s,,.
- 3..,,;,4 -
s :,a. $g
.e
'I D
..hg. ?.
a..e:h *P.. :.b'.y.:. T *-NM. Mt *
,,p a
y.* :
at o o
'. 3%;. *.% ~ f?
- h *.t~ ?-
=.'k
- c. '.re
=g.,,
.,f..7,s W '#,g i
- k... 4 4[ m..s**.(-'.V.,
. 4.,'sa.
~ r
' g v.;.' 7- ~
- ;,}.. '
'.Y.; Ak..("
$-=. p. h #
s
.; y,.
~.
'. -h Se a
~
, ef.'. (. [.
[.*..
Mi@ @iWWEMMWKMKfMFMen2 VW Tn. W W @ M W Wtm w w-m n 4% w :;
'.9
- I1 j.
.-.1
- I-
' [,.... ( -dJg.--l'h.7..-_h
...,} w ~
.j; 4
v.-. -
[r.
e a
'[ e*
._[
.L..
'4--
%V
. r:
. J "_....Q.,h.b
';'i
- = -
. $...... p..g c.'.'p. r ':,b. :.-f f 't:...:d. v n
c j..'". ~. ?.:
- t-M +. W>.;:i.'.
f
..: L',?
- e..
.1
_ -t, s.. -
- e
- M
, g Q.. Q.
v,,
9
~
$_.h 0
D Sanple of 12/4/86 gallons leaked = 124,500 gallons = 4.712E8 c/Md Col.2/nna e
~
4 Cs-137 4.294E-4
- 4.712 E8 mi 2.023E5 uti
/,o 7
=
j s
3 Cs-134 2.797E'4 1.318E5 M3
=
2 31 E-3 c
2-54 9.598E-6 4.523E3
=
2.667E4
/* g 9 E 2 0 Zn-65 5.659E-5
=
f-Q)-60 1.664E-5 7.841E3
/. 9 6 E-2.
=
'Ibtal 3.731ES uCi t;.,
=
= 0.373 Ci M
.l-
'the plant augnented sanpling progran will include routine sanpling D, p '
of the run-pff area fran the yard drainage system East of the cooling
~
towers.
type frequency and location will be dictated by results of analysis' tained.
i
/
mPt g
as O
FozR - ? ?- 74
~
C/7 e
x
".OVg N '
O
L s
Ady j
(
r..
\\
4
...O
. n,ooo _.
4.q,,.
_ fl- -
~'\\
..., p, 9, );
x
(_\\,
p j
y' D"
D
,n n
/
6@ 03 A A A. g Ngp N
p]u w.; s k 2
c a w:
e1
,f r
s
__ g T
kp' J.. ~
lto v.
t
.3, 7
.1
(
\\
6/W 4 4'N'\\ ' gg.J77
'N
/
e o
.. 9
,o 1
N c>
\\/_g j
a~
I x
= - - -
gg
-N f.k 0 y
- \\ %g
...% cc.
4 03
_m.
v w
.! k b Mt. ~i
)
//
M*
e.
h..
/
fe.T N - S 7' lh d/V i
N b
i N
s D
0o i
O%
e$t 2 2 e
=
9 w
(~
E-Y t
G t4
.2~oh 3 E. ? $.
E. SI I,
i h
(
A C
9.h.,
-a
=
-t w
4 Mei_ s.it';4I_3 IE 1
9 c4 dE k
~# '
a $ a.
o-a i
=
=
2 es~
~
3 ts a a aa
$$n, a
w
<u~
2 1
2 2 2 4
r 4
Y b h cI 5 {
CO E
-N
"\\
d
+goom o
r-
~=
6
,h s\\
IJE9"Dr2ML9 U8 f.
[
LOSS OF FUEL POOL INVENTORY ll.
1
(
The following summary describes the sequence of events relating to the loss of approximately five and one-half feet of water from the Unit I and Unit II Spent Fuel - -Storage
- pools, which occurred at approximately 2200 EST on December 3rd, 1986.'
At approximately 2200 on December 2nd, 1986, a p1' ant Equipment Operator closed a
service air hose station valve which he found cracked open while restoring clearances unrelated to this valve.
The l
operator was unaware that this valve was the supply isolation valve to the transfer canal inflatable seal pressure regulator.
The regulator had failed at some unknown previous time and its supply isolation valve had been throttled almost closed to control seal l
pressure.
With the air valve
- isolated, seal air pressure would have started decreasing at a
rate dependent upon seal leakage.
At approximately 1130 EST, on December 3rd, 1986, the Unit 1 operators received the second low fuel pool level alarm for their shift.
As refilling of the fuel pools is normally only required once per shift, an investigation
, was started.
The investigation discovered a
high level dump valve open, which was closed at that time.
At apprextmately 1400, a plant Equipment OperatoE discovered water leaking from around the Reactor Building penetration 2T43-HO12A where it entered the Turbine Building on the 112' elevation.
An investigation determined that the water was entering the sealing material between the Unit II Reactor Building and the Turbine Building and leaking out through the penetration.
At approximately
- 1430, the fuel pool alarm occurred again.
This time, a licensed operator also took part in the system valve lineup review in the plant.
No discrepancies were noted, and"the problem was turned over to the next shift.
The evening shift continued the search for the cause of the loss of fuel pool water by closing additional isolation valves in discharge flow paths off
\\
the fuel pool cooling system.
jxszAp 74 dd I
G L9'JU7J159 U @
f
[
LOSS OF FUEL POOL INVENTORY
('
The following summary describes the sequence of events relating to the loss of approximately five and one-half feet of water from the Unit I and Unit II Spent Fuel -
- Storage
- Pools, which occurred at approximately 2200 EST on December 3rd, 1986?
At approximately 2200 on December 2nd, 1986, a p1'a nt Equipment Operator closed a
service air hose station valve which he found cracked open while restoring clearances unrelated to this valve.
The operator was unaware that this valve was the supply isolation valve to the transfer canal inflatable seal pressure regulator.
The regulator had failed at some unknown previous time and its supply isolation valve had been throttled almost closed to control seal pressure.
With the air valve
- isolated, seal air pressure would have started decreasing at a
rate dependent upon seal leakage.
At approximately 1130 EST, on December 3rd, 1986, the Unit 1 operators received the second low fuel pool level alarm for their shift.
As refilling of the fuel pools is normally only required once per shift, an investigation was started.
The investigation discovered a
high level dump valve open, which was closed at that time.
I At appr'ontmately 1400, a plant Equipment Operator discovered water leaking from around.the Reactor 1
j Building penetration 2T43-HO12A where it entered the Turbine Building on the 112' elevation.
An investigation determined that the water was entering the sealing material between the Unit II Reactor Building and the Turbine Building and leaking out through the penetration.
At approximately
- 1430, the fuel pool alarm occurred again.
This time, a licensed operator also took part in the system valve lineup review in the plant.
No discrepancies were noted, and"the problem was turned over to the next shift.
The evening shift continued the search for the cause of the loss of fuel pool water by closing additional j
isolation valves in discharge flow paths off the fuel pool cooling system.
jqs7AF 76 9 84
-- 1
At cpproximstoly
- 2137, o Shift Sup3rvicor noted
- gg that both fuol. pool cooling pumpn hcd tripped on l ow, low fuel pool surge tank level.
All normal low pool level alarms functioned normally.
At this time, water level in the fuel pools was reported to be approximately~'one foot below the pool skim,mers.
When
-s i nve stD a ti ng----the-- probl==- the Unit I operators 7ef t--&
'/
the ' Control Room reviewed technical specifications and
,f6und that minimum pool level was 8.5 ft. above top of
> active fuel.
p,
(.. 9 At approximately 2200 on December
- 3rd, 1986, several reports to the Control Room occurred:
1)
A Bechtel employee reported water coming into the 112' elevation of the Turbine Building from "the Hp office",
at the condenser bay.
This report was inconsistent as the HP office is on the 130' elevation.
2)
The Health physics Department reported water pouring down out of the cable trays in the Turbine Building hallway.
3)
A plant Equipment Operator attempting to t
check the Unit II Nitrogen storage tank was
(
i una bl e to open the door to the area due to wBt er behind the door.
)
l By approximately
- 2230, fuel pool level had j
decreased approximately five feet below normal level.
At this
- time, the air pressure on the transfer canal i nfi r ': a bl e seals was observed at O psig.
The closed air asolation valve was opened and then throttled to re-establish normal seal pressure.
The depth in the i
fuel pool remained greater than 30 feet of water at all times.
While the refueling floor investigation was occurring, a
second Shift Supervisor forced open the door to the Unit II nitrogen storage tank area.
Inspection of the area revealed water flowing from the seal between the two Reactor buildings up to an elevation six feet above the existing water level.
At this
- time, there was two to three feet of water in the storage tank area.
Water was observed flowing out of
.this area through a
storm drain.
Ef fort s were undertaken to prevent the escape of the water that i
entered the Hot Machine Shop from the nitrogen storage tank area.
Relatively little water was-observed I
1 actually leaking through the outside doors of the Hot
\\
Machine Shop.
I l
(Pego Theso)
~
c
.p At this time, efforts were undertaken to contain t
the water leaving the storm drain system as there was no doubt that the fuel pools were the source of the water entering the nitrogen storage tank area storm drain.
At 2245, the Georgia Power plant Hatch Manager of Operations was notified and immediately responded to the site.
At
- 2255, fuel pool level had been returned to normal.
By
- 2315, the Georgia Power Vice President for Plant Hatch had arrived on site.
At
- 2330, Georgia Power Manager of Health Physics and Chemistry was notified and immediately responded to the site.
At 0128
- EST, December
- 4th, 1986, the NRC was informed of the situation.
o ADDITIONAL FOLLOWUP ITEMS:
o The fuel pool cooling and cleanup system was returned to service at 2400 EST en December 3rd, 1986.
o Health Physics was instructed to begin taking surveys and samples to confirm that l
the contaminated water had not left the site boundaries and to contain and cleanup the contaminated areas in and around the, plant site.
j
,, w 1
1 o
An investigation of the existing alarm
)
equipment related to the transfer canal j
inflatable seal was performed.
The alarm is controlled by level switch G41-NO19 and annuneiates on panel 2H11-P654%,There is no indication that this alarm occurred during this problem and an investigation is in progress into the functional sj;atus of this equipment.
\\
1
o Equipm:nt eloorenco 2-06-1909 w0o accund en
, (p^-
tha ocrvico car cupply volve to the (i
b l
transfer canal inflatable sea l s, tagging the valve I
\\ I open.
o A
review of Unit II Technical Specifications determined that Unit II Technical Specification required 23 feet of water above the top of irradiated fuel when it is stored in the fuel pool racks.
Detailed I
calculations have revealed that the minimum water level reached above the active portion of the fuel was approximately 18.4 ft. of water.
The period of time level was below the technical specification limit was less than 1-1/2 hours (period of time from fuel pool cooling system trips until level was restored to normal).
t 3
H.
L.
Sumner Manager of Operations Date
~
~
"A.'
e e
i i
1 t
se *
\\
9
- s em
o
- ++*++*******++*********************+++***
E.I. Hatch Huclear Plant Radio-Huclide Analysis Program e
- ee***********
Spectrum I.D.
- RAPSP 12/06/86 1126 Comment : Pt.#3 00700 Collection Start D at e :
12/06/86 0700 Count Start Date :
12/06/86 1113 Collection Stop Date :
12/06/86 0700 Clock Time :
600 Secs Live time :
600 secs Library Name : RPLB1 Sample Volume :1.00E+03 mi Geometry code : 1LTB-0 Detector #3 Oper at or 's Initials : RG
. Yield :
1.0000 Energy (kev >=
.23+
1.000*Ch#+ 0.000E+00*Ch#^2+ 0.000E+00*Chea3 : 12/05/86 1622 EFF= 1/[ 2.451E-01+Ea(-2.394E+00) +
6.892E+02*E^( 8.473E-01>3 : 12/01/86 1425 uhere E= Energy in NeV.
APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Nuclide Analysis Program Initial Peak Search Pe ak #
Energy Address Het Error LLD Channels Isotope Flag (Kev)
Channel Counts Counts Counts In Peak ummmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm 1
604.77 604.41 51 8
4 6
Cs-134 2 661.47 661.09 52 8
5 4
Cs-137 3
795.73 795.33 40 7
4 7
Cs-134 4 1332.31 1331.80 14 4
2 4
Co-60 Secondary Peak Search Peak #
Energy Het Error LLD Channels Isotope 2nd Peak (Kev)
Counts Counts Counts In Peak sammmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmsES&ammmmmmmmmmmmmmmmmmmmmmma 1
604.77 51 8
4
.6 Cs-134 2nd Pk HF 2
661.47 52 8
5
.4 Cs-137 3
795.73 40 7
4 7
Cs-134 2nd Pk HF l
4 1332.31 14 4
2 4
Co-60 2nd Pk HF f
g y _.[(7-7[,
Operator Changes 0
I
E.I.
Hatch Nuclear Plant Radio-Huclide Analysis Program Spectrum
!.D.
- RAPSP 12/06/86 1126 Comment : Pt.#3 00700 Collection Start Date :
12/06/86 0700 Count Start Date :
12/06/86 1113 Collection Stop Date :
12/06/86 0700 Clock Time :
600 Secs Live time :
600 secs Library Name : RPLB1 Sample Volume :1.00E+03 ml Geometry code : 1LTB-0 Detector #3 Operator's Initials : RG Yield :
1.0000 Energy (kev >=
.23+
1.000*Ch#+ 0. 000E+00*Ch# ^2+ 0. 000E+00*Ch#^3 : 12/05/86 1622 EFF= 1/[ 2.451E-01*E^(-2.394E+00) +
6.892E+02*E^( 8.473E-01)] : 12/01/86 1425 uhere E= Energy in Nev.
APPLIED PHYSICAL TECHNOLOGY INC.
Padio-Huclide Analysis Program Summary of Analysis CONCENTRATIONS ISOTOPE ENERGY HET ACTIVITY ERROR LLD FLAG (Kev)
(uCi/ml)
(uCl/ml)
(uCi/ml)
Selected Huelides Xe-133 81.00 1.342E-07 1.698E-07 LLD Co-57 122.10 4.316E-08 5.410E-08 LLD Ce-144 133.50 3.205E-07 4.138E-07 LLD Tc-99m 140.50 6.862E-08 7.470E-08 LLD Ce-141 145.40 7.196E-08 1.082E-07 LLD Te-131 149.70 5.827E-05 6.086E-05 LLD Kr-85m 151.20 8.868E-08 1.000E-07 LLD Kr-88 196.30 4.809E-07
--e. 4. 897E-07 LLD Te-134 210.50 1.523E-05 1.600E-05 LLD Te-132 228.16 5.500E-08 6.232E-08 LLD Xe-133m 233.20 3.792E-07 4.965E-07 LLD Xe-135 249.80 7.525E-08
~ 8.689E-08 LLD Xe-138 258.30 1.969E-04
" 2.221E-04 LLD I-134m 271.90 1.223E-04 1.876E-04 LLD Ce-146 317.00 1.441E-04 1.664E-04 LLD Cc-51 320.10 5.403E-07 7.437E-07 LLD Ba-133 356.00 8.219E-08 1.273E-07 LLD Tc-104 358.00 7.084E-05 6.336E-05 LLD I-131 364.50 7.129E-08 8.231E-08 LLD Sn-113 391.70 8.889E-08 1.089E-07 LLD
2r-88 392.90 S.724E-08 7.571E-08 LLD Kr-87 402.60 1.147E-06 1.938E-06 LLD Sb-125 427.89 2.079E-07 2.750E-07 L L-D Zn-69m 438.60 7.662E-08 5.792E-08 LLD i
W-187 479.50 3.053E-07 4.896E-07 LLD 6.903E-08 3.829E-08 LLD Y-87 484.70 5.480E-08 8.489E-08 LLD I-133 529.90 1.535E-07 2.170E-07 LLD Ba-140 537.30 As-76 559.10 1.921E-07 2.148E-07 LLD 1.658E-07 9.287E-08 LLD Ag-110m 657.70 Cs-137 661.47 1.341E-06 2.019E-07 1.199E-07 Measured 3.295E-07 2.854E-07 LLD I-132 667.70 6.241E-07 9.304E-07 LLD Mo-99 739.50 6.338E-08 8.964E-08 LLD 2r-95 756.70 5.607E-08 5.015E-08
'L L D Hb-95 765.80 Cs-134 795.73 1.219E-06 2.147E-07 1.306E-07 Measured 0.000E+00 5.283E-08 LLD Co-58 810.80 4.636E-08 7.570E-08 LLD Cs-136 818.50 7.605E-08 1.423E-07 LLD Mn-54 834.80 0.000E+00 2.933E-07 LLD Te-131m 852.20 1.291E-06 2.582E-06 L-L D I-134 884.10 0.000E+00 2.765E-07 LLD Hp-238 984.45 0.000E+00 1.412E-04 LLD Rb-89 1932.00 Fe-59 1999.00 8.573E-08 1.212E-07 LLD 2n-65 1116.00 1.174E-07 1.918E-07 LLD 2.090E-07 4.179E-07 LLD I-135 1260.00 Ha-22 1275.00 5.445E-08 7.701E-08 LLD I
Ar-41 1294.00 0.000E+00 4.011E-07 LLD Co-60 1332.31 5.456E-07 1.591E-07 9.219E-08 Measured 0.000E+00 2.121E-05 LLD 4
Cu-64 1346.00 4.982E-08 9.965E-08 LLD Ha-24 1369.00 Sr-92 1304.00 1.375E-07 2.751E-07 LLD 0.000E+00 2.869E-05 LLD J
Cs-138 1436.00 0.000E+00 1.213E-06 LLD Hi-65 1482.00 0.000E+00 6.364E-07 LLD K-42 1525.00 0.000E+00 1.050E-07 LLD La-140 1596.00 0.000E+00 2.052E-07 LLD Sb-124 1691.02 0.000E+00 1.208E-06 LLD Mn-56 1811.00 0.000E+00 6.041E-04 LLD Rb-88 1836.00 Other Quant i t at ive Pe ak s Hone Secondary and Identified Peaks Counts /ml/Sec Cs-134 604.77 3.833E-02 5.870E-03 3.361E-03 Id Unk nown Peak s Counts /ml/Sec Hone
______________________________________________________________________w_________
-- v i
i e
e l
- +************************+++
E.I.
Hatch Nuc lear Pl ant Radio-Huclide Analysis Program Spectrum I.D.
- RAPSP 12/06/86 1115 Comment : Pt.#4 00700 Collection Start Date :
12/06/86 0700 Count Start D at e :
12/06/86 1102 Collection Stop Date :
12/06/86 0700 Clock Time :
600 Secs Live time :
600 secs Library Name : RPLB1 Sample Volume :1.00E+03 ml Geometry code : 1LTB-0
. Detector #3 Operator's Initials : RG Yield :
1.0000 Energy (kev)=
.23+
1.000*Ch#+ 0.000E+00*Ch#^2+ 0.000E+00*Ch#^3 : 12/05/86 1622 EFF= 1/[ 2.451E-01*E^(-2.394E+00) +
6.892E+02*E^( 8.~473E-01>3 : 12/01/86 1425 uhere E= Energy in Nev.
APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Nuclide Analysis Program Initial Peak Search Peak #
Energy Address Het Error LLD Channels Isotope Flag (Kev)
Channel Counts Counts Counts In Peak 1
605.00 604.64 35 7
4 8
Cs-134 2 661.57 661.19 29 6
3 4
Cs-137 3 795.77 795.37 26 5
2 4
Cs-134 Secondary Pe ak Search Peak #
Energy Het Error LLD Channels Isotope 2nd Peak (Kev)
Counts Counts Counts In Peak
...................................................ww=====......................
1 605.00 35 7
4
. 8 Cs-134 2nd Pk NF 2
661.57 29 6
3 4
Cs-137 3
795.77 26 5
2
,, 4 Cs-134 2nd Pk HF Operator Changes
E.I. Hatch Nuclear Plant Radio-Nuclide Anal
............................ysis Program
)
Spectrum I.D.
- RAPSP 12/06/86 1115 Comment : Pt.#4 00700 Collection Start Date :
12/06/86 0700 Count Start Date :
12/06/86 1102 i
Collection Stop Date :
12/06/86 0700 Clock Time :
600 Secs Live time :
600 secs Library Name : RPLB1 Sample Volume :1.00E+03 mi Geometry code : 1LTB-0 Detector #3 Operator's Initials : RG Yield :
1.0000 Energy (kev)=
.23+
1.000.Ch#+ 0. 000E+00.Ch# ^2+ 0. 000E+00.Ch#^3 : 12/05/86 1622 EFF= 1/C 2.451E-01.E^(-2.394E+00) 6.892E+02.E^( 8.473E-01)3 : 12/01/86 1425
+
uhere E= Energy in Nev.
k APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Nuclide Analysis Program Summary of Analysis CONCENTRATIONS ISOTOPE ENERGY HET ACTIVITY ERROR LLD FLAG (Kev)
(uCi/ml)
..........................................(uCi/ml)
(uCi/ml) l Selected Nuclides Xe-133 81.00 1
1.199E-07 1.434E-07 LLD Co-57 122.10 3.826E-98 4.614E-08 LLD
(
Ce-144 133.50 3.069E-07 3.926E-07 LLD l
Tc-99m 140.50 5.907E-08 5.782E-08 LLD Ce-141 145.40 6.186E-98 6.709E-08 LLD Te-131 149.70 3.429E-95 4.427E-05 LLD Kr-85m 151.20 6.366E-08 8.219E-08 LLD Kr-88 196.30 3.966E-97 3.958E-07 LLD Te-134 210.50 9.430E-06 1.054E-05 LLD Te-132 228.16 4.666E-08 5.820E-08 LLD Xe-133m 233.20 3.915E-07
.-4 502E-97 LLD Xe-135 249.80 5.866E-08 9.088E-08 LLD Xe-138 258.30 1.571E-94 2.221E-04 LLD I-134m 271.90 1.196E-04 1.186E-04 LLD Ce-146 317.00 1.177E-04
~1.557E-04 LLD Cr-51 320.10 5.679E-07
7.436E-07 LLD Ba-133 356.00 7.652E-98 1.040E-07 LLD l
Tc-104 358.00 6.336E-05 8.961E-05 LLD 1-131 364.50 5.569E-98 7.509E-08 LLD
)
Sn-113 391.70 6.666E-08 9.938E-00 LLD 2r-88 392.90 4.292E-08 6.399E-08 LLD Kr-87 402.60 7.844E-07 7.844E-07 LLD Sb-125 427.89 1.644E-07 2.324E-07 LLD I
l 2n-69a 438.60 6.087E-08 8.116E-08 LLD W-187 479.50 1.815E-07 1.623E-07 LLD Y-87 484.70 4.682E-08 6.621E-08 LLD 4.219E-08 6.889E-08 LLD I-133 529.90 Ba-140 537.30 2.657E-07 4.339E-07 LLD As-76 559.10 1.265E-07 1.912E-07 LLD 1.113E-07 4.643E-08 LLD Ag-110m 657.70 Cs-137 661.57 7.526E-07 1.476E-07 7.340E-08 Measured I-132 667.70 2.810E-07 2.700E-07 LLD Mo-99 739.50 2.936E-07 4.153E-07 LLD Zr-95 756.70 7.762E-08 1.268E-07 LLD Hb-95 765.80 5.014E-08 7.091E-08 LLD Cs-134 795.77 7.960E-07 1.584E-07 4.936E-08 Measured Co-58 810.80 5.283E-08 9.150E-08 LLD Cs-136 818.50 5.982E-08 7.567E-08 LLD 6.012E-08 9.314E-08 LLD Mn-54 834.80 1.460E-07 2.920E-07 LLD Te-131m 852.20 1.934E-06 3.159E-06 LLD I-134 884.10 Hp-23s 984.45 0.000E+00 2.758E-07 LLD 7.061E-05 1.412E-04 LLD Rb-89 1932.00 Fe-59 1999.00 8.572E-08 1.212E-07 LLD 1.356E-07 2.349E-07 LLD 1
2n-65 1116.00 I-135 1260.00 0.000E+00 4.100E-07 LLD 0.000E+00 7.701E-08 LLD Ha-22 1275.00 Ar-41 1294.00 1.871E-07 3.741E-07 LLD Co-60 1332.00 5.645E-08 7.983E-88 LLD Cu-64 1346.00 0.000E+00 2.100E-05 LLD i
Ha-24 1369.00 0.000E+00 9.881E-08 LLD l
Sr-92 1384.00 0.000E+00 2.625E-07 LLD l
Cs-138 1436.00 0.000E+00 2.264E-05 LLD Hi-65 1482.00 0.000E+00 1.153E-06 LLD K-42 1525.00 0.000E+00 6.299E-07 LLD La-140 1596.00 0.000E+00 1.047E-07 LL D Sb-124 1691.02 1.451E-07 2.902E-07 LLD Mn-56 1811.00 0.000E+00 1.150E-06 LL.D Rb-88 1836.00 0.000E+00 6.041E-04 LLD Other Quant i t at i ve Peak s l
Hone Secondary and Identified Peaks Counts /ml/Sec Cs-134 605.00 2.631E-02 5.005E-03 3.007E-03 Id Unknown Peaks Counts /ml/See Hone
__ e.
t e
~..
Etw2.
J 5/ P75
...................* e....**..**..........**...
E.I. Hatch Nuclear Plant Radio-Nuclide Analysis Pro
...***....***.*e.****....**.*****.e.
gram Spectrum I.D.
- RAPSP 12/06/86 1105 Comment :
Pt."A" 00700 Collection Start Date :
12/06/86 0700 Count Start Date :
12/06/86 105e Collection Stop Date :
12/06/86 0700 Clock Time :
600 Secs Live time :
600 secs Library Name : RPLB1 Sample Volume :1.00C+03 mi Geometry code : 1LTB-0 Detector #3 Operator's Initials : RG Yield :
1.0000 Energy (kev)=
.23+
1.000*Che+ 0.000E+00.Ch#^2+ 0.000E+00.Ch#^3 : 12/05/86 1622 EFF= 1/C 2.451E-01.Ea(-2.394E+00)
+
6.892E+02*E^( 8.473E-01)3 : 12/01/86 1425 uhere E= Energy in MeV.
APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Huclide Analysis Program Initial Peak Search Peak #
Energy Address Net Error LLD Channels Isotope Flag (Kev)
Channel Counts Counts Counts In Peak E533335533535355555835EB35353333333333533333333E53533333333333333553333333333333 1
604.88 604.52 16 4
3 3
Cs-134 2 661.61 661.24 37 6
2 7
Cs-137 3
795.90 795.50 22 5
3 5
Cs-134 Secondary Peak Search Peak #
Energy Net Error LLD Channels Isotope 2nd Peak (Kev)
Counts Counts Counts In Peak
....................................................=17........................
1 604.08 16 4
3 3
Cs-134 2nd Pk HF 2
661.61 37 6
2
.7 Cs-137 3
795.90 22 5
3 5
Cs-134 2nd Pk HF 1
Operator Chances J
=
E.I.
Hatch Nuclear Plant Radio-Huclide Analysis Program Spectrum I.D.
- RAPSP 12/06/86 1105 Comment :
Pt."A" 00700 Collection Start Date :
12/06/86 0700 Count Start Date :
12/06/86 1950 Collection Stop Date :
12/06/86 0700 Clock Time :
600 Secs Live time :
600 secs Library Name : RPLB1
'1 Sadp'l e Vo l'u'me ' : 1.~ 00f+03 ' m'1'
^ ~
~
Geometry code : 1LTB-0 Detector #3 Operator's Initials : RG Yleid :
1.0000 Energy (kev)=
.23+
1.000*Ch#+ 0.000E+00*Ch#^2+ 0.000E+00*Che^3 : 12/05/86 1622 EFF= 1/C 2.451E-01*Ea(-2.394E+00) +
6.892E+02*E^( 8.473E-01)] : 12/01/86 1425 uhere E= Energy in MeV.
APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Huclide Analysis Program Summary of Analysis CONCENTRATIONS 1SOTOPE ENERGY HET ACTIVITY ERROR LLD FLAG (Kev)
(uCi/mi)
(uCi/mi)
( u C i / a.1 )
====================================================================
Selected Nuclides Xe-133 81.00 1.062E-07 1.358E-07 LLD Co-57 122.10 3.555E-08 4.614E-08 LLD Ce-144 133.50 2.926E-07 3.761E-07 LLD Tc-99m 140.50 5.210E-08 4.377E-08 LLD Ce-141 145.40 6.364E-08 9.487E-08 LLD Te-131 149.70 3.175E-05 3.175E-05 LLD Kr-85m 151.20 6.667E-08 7.127E-08 LLD l
Kr-88 196.30 3.769E-07 4.460E-07 LLD Te-134 210.50 7.484E-06 7.729E-06 LLD Te-132 228.16 4.527E-08
.,5.818E-08 LLD Xe-133m 233.20 4.729E-07
' 6.377E-07 LLD Xe-135 249.80 4.475E-08 5.168E-08 LLD Xe-138 258.30 1.877E-04 2.655E-04 LLD l
9.380E-05 8.389E-05 LLD I-134m 271.90 Ce-146 317.00 1.316E-04 LLD 8.825E-05 Cr-51 320.10 3.918E-07 4.292E-07 LLD Ba-133 356.00 6.366E-08 1.200E-07 LLD Tc-104 358.00 6.336E-05 7.317E-05 LLD I-131 364.50 4.110E-08 5.812E-08 LLD Sn-113 391.70 6.666E-08 7.697E-08 LLD 2r-88 392.90 4.047E-08 4.956E-08 LLD Kr-87 402.60 7.024E-07 8.615E-07 LLD Sb-125 427.89 1.724E-07 2.750E-07 LLD
t 2n-69a 438.60 3.479E-08 4.017E-08 LLD W-187 479.50 1.614E-07 2.282E-07 LLD Y-87 484.70
)
4.674E-08 5.397E-08 LLD I-133 529.90 5.926E-08 6.381E-08 LLD Ba-140 537.30 2.168E-07 1.533E-07 LLD Rs-76 559.10 1.063E-07 9.509E-08 LLD Rg-110m 657.70 1.161E-07 4.643E-08 LLD Cs-137 661.61 9.560E-07 1.628E-07 5.607E-08 Measured I-132 667.70 2.646E-07 1.468E-07 LLD Mo-99 739.50 0.000E+00 4.144E-07 LLD Zr-95 756.70 7.761E-08 8.962E-08 LLD Hb-95 765.80 5.014E-08 5.014E-08 LLD Cs-134 795.90 6.500E-07 1.544E-07 9.560E-08 Neasured Co-58 810.80 4.575E-08 7.470E-08 LLD Cs-136 818.50 3.782E-08 5.348E-08 LLD Mn-54 834.80 3.802E-08 7.605E-08 LLD Te-131m 852.20 2.055E-07 2.907E-07 LLD I-134 884,10 1.652E-06 1.907E-06 LLD Np-238 984.45 2.382E-07 2.750E-07 LLD Rb-89 1932.00 7.061E-05 1.412E-04 LLD Fe-59 1999.00 6.061E-08 1.212E-07 LLD Zn-65 1116.00 1.174E-07 1.918E-07 LLD I-135 1260.00 0.000E+00 4.015E-07 LLD Na-22 1275.00 3.850E-08 7.701E-08 LLD Ar-41 1294.00 1.734E-07 3.468E-07 LLD Co-60 1332.00 6.913E-08 7.983E-08 LLD Cu-64 1346.00 0.000E+00 2.077E-05 LLD Ha-24 1369.00 4.895E-08 9.790E-08 LLD Sr-92 1384.00 0.000E+00 2.494E-07 LLD Cs-138 1436.00 0.000E+00 1.749E-05 LLD Hi-65 1482.00 0.000E+00 1.092E-06 LLD K-42 1525.00 0.000E+00 6.229E-07 LLD La-140 1596.00 0.000E+00 1.043E-07 LLD Sb-124 1691.02 1.026E-07 2.052E-07 LLD Mn-56 1811.00 5.450E-07 1.090E-06 LLD Rb-88 1836.00 0.000E+00 6.041E-04 LLD Other Quantitative Peaks None Secondary and Ident i fi ed Peak s, Counts /mi/Sec Cs-134 604.88 1.165E-02 3.298E-03 2.377E-03 Id Unknoun Peaks Counts /ml/Sec Hone No e
ee
~ -
E. I. Hatch Nuclear Plant l
Radio-Nuclide Analysis Program l
l l
Spectrum I.D.
- RAPSP i
l 12/06/86 1138 Comment :
Pt."B" 90700 Collection Start Date :
12/06/86 0700 Count Start Date :
12/06/86 1124 Collection Stop Date :
12/06/86 0700 Clock Time :
600 Sees Liue time :
600 secs Library Name : RPLB1 Sample Volume :1.00E+03 m1 Geometry code : 1LTB-0 Detector #3 Operator's Initials : RG Yield :
1.0000 Energy (kev)=
.23+
1.000*Ch#+ 0.000E+00*Che^2+ 0.000E+00*Ch#^3 : 12/05/86 1622 EFF= 1/[ 2.451E-01*E^('-2.394E+00)
+
6.892E+02*E^( 8.473E-01)3 : 12/01/86 1425 uhere E= Energy in MeV.
APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Huclide Analysis Program Initial Pe ak Search Peak #
Energy Address Het Error LLD Channels Isotope Flag (Kev)
Channel Counts Counts Counts In Peak WE EE EEE ESBE EEEEEEEE EE EE E EEE E EEEEEEEEEEEEE E E E E E E E E E E EE EEE EEEEEE EE E B3E33333 333 3 333 i
Secondary Peak Search Peak #
Energy Het Error LLD Channels Isotope 2nd Peak (Kev)
Counts Counts Counts In Peak mEE ssa mmEmEssanssuma s EsazEmEm msEaEEssEE EmaE m u B asammaEE mmE mm uBmEEasEEBu mmBammEEas
--g.
Operator Chances
E.1. Hatch Huc lecr Plant e
o Radio-Huclid: Analysis Program e
Spectrum I.D.
- RAPSP l
12/06/86 1138 Comment :
Pt."B" 00700 Collection Start Date :
12/06/86 0700 Count St art Dat e :
12/06/86 1124 Collection Stop Date :
12/06/86 0700 Clock Time :
600 Sees Live time :
600 secs Library Name : RPLB1 Sample Volume :1.00E+03 al Geometry code : 1LTB-0 Detector #3 Operator's Initials : RG Yield :
1.0000 Energy (kev)=
.23+
1.000*Cht+ 0.000E+00*Ch#^2+ 0.000E+00*Che^3 : 12/05/86 1622 EFF= 1/C 2.451E-01*Ea(-2.394E+00) +
6.892E+02*E^( h.473E-01)3
- 12/01/86 1425 where E= Energy in MeV.
APPLIED PHYSICAL TECHNOLOGY INC.
Radio-Huclide Analysis Program Summary of Analysis CONCENTRATIONS ISOTOPE EHERGY HET ACTIVITY ERROR LLD FLAG (Kev)
(uCi/ml)
(uCi/ml)
(uCi/ml)
BEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEMBEEEESPEEUEEEEEEEEEEEEEEEEEEEEEEEEEEBRE Selected Huclides Xe-133 81.00 6.814E-08 4.542E-08 LLD Co-57 122.10 1.631E-08 1.631E-08 LLD Ce-144 133.50 1.463E-07 1.309E-07 LLD Tc-99m 140.50 3.016E-08 2.697E-08 LLD Ce-141 145.40 3.676E-08 4.245E-68 LLD Te-131 149.70 2.778E-05 2.404E-05 LLD Kr-85m 151.20 5.501E-08 7.7GOE-08 LLD Kr-88 196.30 3.210E-07 5.121E-07 LLD l
Te-134 210.50 8.981E-06 1.176E-05 LLD Te-132 228.16 3.121E-08 4.414E-08 LLD I
Xe-133m 233.20 2.488E-07 2.873E-07 LLD Xe-135 249.00 2.698E-08 4.406E-08 LLD Xe-138 258.30 8.395E-05 8.395E-05 LLD 1-134m 271.90 5.932E-05 1.027E-04 LLD A
5.883E-05 5.883E-05 LLD Ce-146 317.00 Cr-51 320.10 2.147E-07 3.507E-07 LLD 3.676E-08
~P*~6.002E-88 LLD Ba-133 356.00 3.658E-05 3.653E-05 LLD Tc-104 358.00 3.363E-88 5.824E-08 LLD I-131 364.50 3.143E-08 6.286E-08 LLD i
Sn-113 391.70 2.024E-08 2.862E-88 LLD Zr-88 392.90 l
Kr-87 402.60 4.789E-07 6.773E-07 LLD 5.198E-08 1.040E-07 LLD Sb-125 427.89 i
Zn-69m 438.60 2.067E-08 4.134E-08 LLD 1.160E-07 1.641E-07 LLD W-187 479.50 2.712E-88 3.835E-88 LLD Y-87 484.70 2.487E-00 4.931E-08 LLD I-133 529.90 1.886E-07 1.535E-07 LLD Ba-140 537.30 4.826E-08 9.G51E-08 LLD As-76 559.10
Ag-110m 657.70 3.284E-08 4.644E-08 LLL Cc-137 661.60 3.670E-08 5.191E-08 LLD I-132 667.70 1.508E-07 1.741E-07 LLD Mo-99 739.50 2.084E-07 4.169E-07 LLD Zr-95 756.70 4.482E-08 8.964E-00 LLD Hb-95 765.80 3.547E-08 5.016E-08 LLD Cs-134 795.80 3.023E-08 6.046E-08 LLD Co-58 810.80 2.642E-08 5.284E-08 LLD Cs-136 818.50 5.355E-08 5.355E-08 LLD Mn-54 834.80 2.689E-08 5.378E-08 LLD Te-131m 852.20 0.000E+00 2.945E-07 LLD I-134 884.10 0.000E+00 2.984E-06 LLD Hp-238 984.45 0.000E+00 2.772E-07 LLD Rb-89 1932.00 1.223E-04 1.412E-04 LLD Fe-59 1999.00 0.000E+00 1.213E-07 LLD Zn-65 1116.00 9.589E-08 1.356E-07 LLD I-135 1260.00 0.000E+00 4.260E-07 LLD Ha-22 1275.00 0.000E+00 7.701E-08 LLD Ar-41 1294.00 2.150E-07 4.300E-07 LLD Co-60 1332.00 3.991E-08 7.983E-08 LLD Cu-64 1346.00 4.000E+00 2.143E-05 LLD Ha-24 1369.00 5.025E-08 1.005E-07 LLD Sr-92 1384.00 0.000E+00 2.883E-07 LLD Cs-138 1436.00 0.000E+00 3.635E-05 LLD Hi-65 1482.00 0.000E+00 1.276E-06 LLD K-42 1525.00 0.000E+00 6.430E-07 LLD La-140 1596.00 0.000E+00 1.053E-07 L L'D Sb-124 1691.02 1.026E-07 2.053E-07 LLD Mn-56 1811.00 0.000E+00 1.269E-06 LLD Rb-88 1836.00 0.000E+00 6.041E-04 LLD Other Quantitative Peaks None Secondary and Identified Peaks Counts /ml/Sec Hone Unknown Peaks Counts /mi/Sec Hone
.- e.
i e
Table.
.1 5w.,,
.ca.,,ie
&.soi,o at c~ ~
sp e c.1,,-py rne<>aremed.s
- a. +
Pt,t iMe % Dete..,sec G,ITe6 nple loc
+>cn Nue />de.
Gne<,M R=
[AG*/mN Ar <
(b'oe-ec<c yto n l ACCnJr<,
WC-n onc /;ke ow-sc/// )
{ valve f o n sb. >~ )
(Valve f 04 c Si3'> Y
- $f}
C.S. /34-
/ 2 2 ! o. 2.1 E%
8 57!o.ze E '7 Cs-n7
- l. 5 + 2 0 N E~&
I 30 2 0.0.% E-G
^
5f
......G 5 15. 4..
7 % !._t. s e E,- 7 2.952 0./7 E-7 Cs-i37 7 53 $ /.45 Ek7 4.f2.f o /7 E-7
--.A..--.......-..-.
S'13+
fo. 50 _2 I. 5~4. 2-7
+. GG 2 o 23 E J
... - G -!37
.s sc.2 t.(s3.E-7 (r.so 2 0 26 E-7 lll; @il:,, l j.lil! h i: wrW6
<= ovc/Mc.5 h*4... m :.m &>.de*th n
k&+a
.!s;..
........+!
in :
. Iii((!!!
- 4
4 AII. I,'cessa.
a nst.se s are y
perked s+
PI J % hk, e<c h me<>, sten, &
- S W'0-Pn.
- .63..-Hnse o{
W AM 5.
All. A/8C.
%p> __ c<<<<
Pe4.med in D e R ey ;a,.21' co.,diy.),bo. -k>y,
. cseL..ge+ ceme,+ w,s 6,. sed c~d73 H~
o f 5 0 0 0 ser e s.
on a.
FsZR-27-76
c
/.
I r
I t
h"97C//
ft-e/ Paa/
8p;//
SD - -~ y -
/ s/*'~
/ 4,gJJ rc/cn.e de5Hmks)
S+
< / 4 1,
.5ba yllo,5
/os-/-
fo-h / pon / '
~ 17, scoy. -lo red-~.$c' 1.
2 Ec, co: y.
S~n~p bid s.
3 4't, coc y.
be,Gu, J
b.my, ca:e reIcwa = c.323 G (bueJ os, 1 2 4, g c c y llo,s Rz) c Z
To cond,;,
<3 ncs e4 4, b -.,.' a, s.4d t-v r-/c -
Icavi,3 sh-~
d er,'
T s k ~,
<-I y
j'<=s i b / c,
c~-
Seeles of M
c a +4 c.,
de-1 m.a hv.' N-a h,3 1%.
Grec k.
bed
~kk4 lcd 1 -/*
-hf-e.
Em m,e.
7h..
wk.-
+4&
can co,Mn cs
-, e po,d.s re:c )+
es n
O con +~c-N,3 d,.s c, < s jx-ped o'n h v c c o, y //c,
csp,c; 17
+<,/ce.-
h ells foc s~6se p,+
d :spo.rs. /.
L:cex<.
-/=
dqcse 46_
+;se w k.-
i lig.s ca n pin,,;,3 ys k -.,, p uareq= mn+l%. +ced-e,9 sys k,
c<aw ~sse h ee % l-s co JIL 8
I,< -d ie a d d, -H e,,. /
ucim e4 curic c A
ple,
my :
rf
.A co,1, ~;,4 a.
cra -
c~/a
~/
he
-frcrkd,
-l %,
-f%.
eph'c, c~.c.,14....be*_
.. i.
rsm.
rep <es a s m se-ptes 6.-
+, w>
-k, 4%
........G) -l c. cc,ceM'o, (Typ;c~)
M o. m s,* /,oc o y /l,>
L~ r s c
c-G24 nc%N/H *,-th.5?Jc).,.
~
.z.
I?cte<se L
%, k'ec co,%ts s',h
& __ d is e k, y e ca,~G o%hiny aMihw/
g-ptes e.+
tt<.
h cfo - ), n : L ~ ' 7. -., < k l c L
_ e f.
< c l e 's <. ~ T h ;J L
.WI$.. W ffph.E. 5s
<~
Q.k.____rcIcw:.
066 d ;sc 4,9 <
pe~; h.
fo2 s =8g-n 6/G
m.
Z ~.
3, 4
a l
inla. $
Ac'Tlod $7'97f67~
e 5'IS~t /...? I_di' h 5 ASL_l
. P' ~+
fad 0"" N
'3 0
is
_ cl cM- -cd._(v/s _f* +~ed' h*
" i E
-Me.
h J
sk e44 %+
pc-un +
fo,
-hh.
s;-le Mx clic t
.59,d, f
a -}c~
edCed5 O./6 enrem w P> ~
p-epn tp-l-
..b
-fk G,ni15io, b Ul wr>
+'
S clie-}-
NJ ap p,<.Ajey K Iimif.
+;fj g2 cs e T,p/cg/ _
9y,e, /cd t w lro, m h.l
~
G }<-< vc.)
oa 9s b
p,iis/es h __1, cue. :
y c 4 Seuc ~p c.a s k <
5% p/iy P.~j<< m - w/9 p/,.d e d & //
~p Scd:~,/-
S w p/;3,
' er cy ed-Su.cfnet. c-v < + c.,
- t., g c h R c,,
' < ^) <
d e%.-h +c
~ -p/e) h 5%g/c <-
L.S 4,es_5 c,-f Sa%f Co r g.,, __
srs,nj
> t o /-
4-
.Lun ~ya cask-
.S up/c.s tm ;k-;3, ef ou;y al Preurtry _
io
&. pcaes.s of k
dest +
,y s9-;nc~+
.'bo hpiu -e,, t s;s f._.
y 7.(hwa r*leucd m_.*r:n I 14 o
l=>. >
ac+ivHy num+1...~ D.YI nawy atews i
zek#7?.
s < c e -.'- -
~'
L CE-b$ l'M.__
7 9, coa - So, oxy //o,s (a) d 111ec4d.
~
w,,
sti e,&-
h,, bee, -/<c, /cd )
I i
p O Sec 6
(cC' bru 09-DEC-06 09:31:17 I
I LIQUID SAMPLE HATCH PT-3 SN 1296 I
SAMPLE DATE:
06-DEC-86 07:00:00 SAMPLE IDENTIFICATION:
SN1296 TYPE OF SAMPLE:
LIQUID SAMPLE QUANTITY:
1000.000 UNITS:
ML l
SAMPLE GEOMETRY:
SH-0 EFFICIENCY FILE NAME:
EFF2
.LMAR l
ACQUIRE DATE: 09-DEC-06 00:07:02
- FWHM(1332) 1 948 PRESET TIME (LIVE):
5000. SEC
- SENSITIVITY:
5.000 ELAPSED REAL TIME:
5001. SEC
- SHAPE PARAMETER : 10.0 %
ELAPSED LIVE TIME:
5000. SEC
- NBR ITERATIONS:
10.
DETECTOR: GE-2
- LIBRARY:NUCL. MASTER CALIB DATE:
09-DEC-06 07:33:55
- ENERGY TOLERANCE:
1.500KV KEV /CHNL:
0.4999196
- HALF LIFE RATIO:
0.00 0FFSET:
0.0017126 KEV
- ADUNDANCE LIMIT:
00.00%
0.
COEFF. :
4.600E-00 KCU/C**2 *
(
I
?t*
i Fbn 07~7 fa e//V l
ENERCY WINDOW 25.00 TO 2040.46 PK IT ENERGY AREA DKUND FWHM CllANNEL LEFT PW CTS /SEC % ERR FI?
1 3
72.62 148.
15.
1.26 145.27 142 23 2.96E-02 12.7 2.72E 2
3 74.42 170.
93.
1.02 140.07 142 23 3.40E-02 19.3 3
3 76.40 108.
196.
2.24 152.02 142 23 2.16E-02 35.1 4
3 79.16 60.
260.
1.05 150.34 142 23 1.20E-02 53.8 5
3 563.56 168.
77.
2.25 1127.17 1123 28 3.37E-02 12.2 1.79E 6-3 569.53 263.
03.
1.55 1139.12 1123 28 5.25E-02 9.4 7
0 604.95 1403.
157.
1.34 1209.95 1204 14 2.97E-01 3.3 8
0 661.92 1866.
100.
1.35 1323.00 1310 14 3.73E-01 2.6 9
3 796.15 1048.
16.
1.50 1592.32 1585 32 2.10E-01 3.2 1.15E 10 3
302.17 107.
14.
1.56 1604.35 1585 32 2.13E-02'12.9 11 0 1116.05 101.
30.
2.09 2231.98 2223 20 2.02E-02 17.3 12 0 1173.60 95.
11.
1.19 2347.06 2343 11 1.90E-02 12.6 13 0 1332.75 70.
14.
1.09 2665.25 2657 10 1.41E-02 15.9 14 0 1365.29 43.
10.
1.51 2730.32 2723 14 8.54E-03 20.6 15 0 1399.86 27.
13.
1.05 2799.43 2794 16 5.35E-03 31.8 16 0 1460.79 54.
16.
2.61 2921.24 2916 19 1.00E-02 23.4 17 0 1744.40 15.
O.
0.62 3520.20 3510 16 3.00E-03 45.7 PEAK SEARCH COMPLETED (REV 15.1) 1 4
We C
e 9e
+
NUCt.IDE IDENTIFICATION SYSTEM (REV 12/04)
NUCLIDE LINE ACTIVITY REPORT PAGE 1
ACTIVA 1 ION PRODUCT 1 SIGM3 NUCLIDE GDHR ENERGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR; i
MN-52 AP 744.20 0.
O.
85 00 0.000E-01 0.000E 0
0.000E 840.40 0.
O.
3 20 0.000E-01 0.000E O
0.000E 935.60 0.
O.
94.00 0.000E-01 0.000E O
0.000E i
1333.80 70.
14.
5.10 4.913E-01 2.207E -6 3.505E -
1434.40 0.
O.
100 00*
0.000E-01 0.000C 0
0.000E
[
- 11. 100.00 5.501E-01 9.345E -0 1.100E -
1332.49 70.
- 14. 100.00*
4.913C-01 7.738E -8 1.229E ZN-65 AP 1115.52 101.
30.
50.75*
5.753E-01
- 1. 086E, ~7-3.267E NI-55 AP 366.27 0.
O.
4.60 0.000E-01 0.000E 0
0.000E 1115.53 101.
30.
14.80 5,753C-01 4.105E 2
7.248E I
1481.04 0.
O.
23.50*
- 0. 000E -01 0.000E
.0 0.000E AG-76 AP 559.10 0.
O.
44.70*
0.000E-01 0.000E O
0.000E 1
i 563.23 168.
77.
1.20 1.055E 00 5.'020E ~5 6 107E -
657.03 0.
O.
6 10 0.000E-01 0.000E O
0.000E f
1212.72 0.
O.
1.60 0.000E-01 0.000E O
0.000E j
1216.02 0.
O.
3.80 0.000E-01 0.000E O
0.000E l
1220.52 0.
O.
1.40 0.000E-01 0.000E 0
0.000E l
SB-122 AP
-563.93 168.
77.
70.60*
1.055E 00 2.675E -7 3.254E j
W -107 AP 72.06 148.
15.
11.90 2.053E 00 2.704E -6 3.544E 1
134.22 0.
O.
9.40 0.000E-01 0.000E O
0.000E
]
479.55 0.
O.
23.40 0.000E-01 0.000E O
0.000E i
551.55 0.
O.
5.40 0.000E-01 0 000E O
0.000E 610.37 0.
O.
6.70 0.000E-01 0.0000 0
0.000E 685.81 0.
O.
29.20*
0.000E 0.000E 0
0.000E l
FIGGION PRODUCT 1 SICHA NUCLIDE SDHR ENERGY ARCA BKGND
%ABN
%EFF UCI / UNIT ERROR B R -- 0 2 FP 221.45 0.
O.
2.30 0.000E-01 0.000E 0
0.000E 554.32 0.
O.
70.40 0.000E-01 0.0000 0
0.000E 4
i 606.30 1483.
157.
1.20 9.906E-01 2.073E ~4 9.368E I
619.07 0.
O.
43.10 0.000E-01 0.000E O
0.000C 698.33 0.
0.
27.90 0.000E-01 0.000E 0
0.000E i
776.49 0.
O.
03.40*
0.000E 0.000E O
0.000E i
827.81 0.
O.
24.20 0.000E-01 0 000E 0 -0.000E j
1007.57 0.
O.
1.30 0.000E-01 0.000E O
0.000E 1043.97 0.
O.
27.40 0.000E-01 0.000E O
0.000E-1317.47 0.
O.
26.90 0II00E-01 0.000E 0
0.000E 1474.02 0.
O.
16.60 0.000E-01 0.000E 0
0 000E BR 84 FP 002.20 107.
14.
6.10 7.714E-01 0.935E 35 1.155E 3' I
881.60 0.
O.
42.00*
0.~000E-01 0.000E 0
0.000E 1015.90 0.
O.
6.20 0'.'000E-01 0.000E 0 '0.000E 1897.60 0.
O.
14.90 0.000E-01 0.000E O
0.000E i
l'
-,,. - ~. _. - _ _ _
NUCLIDE IDENTIFICATION SYSTCM (RCV 12/04)
NUCLIDE LINE ACTIVITY REPORT PAGE 2
FISSION PRODUCT 1 SIGMA NUCLIDE GDHR ENERGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR SB-127 FP 252.40 0.
O.
0.50 0.000E-01 0.000E O
O.000E i
290.80 0.
O.
2.00 0.000E-01 0.000E O
0.000C 412.10 0.
O.
3.80 0.000E-01 0.000E O
0.000E 445.10 0.
O.
4.30 0.000E-01 0.000E O
0.000C 473.00 0.
O.
25.70 0.000E-01 0.000E O
0.000E-543.30 0.
O.
2.90 0.000E-01 0.000E O
0.000E 603.50 1403.
157.
4.40 9.906E-01 3.200E -5 1.043E -
685.70 0.
O.
36.60*
0.000E-01 0.000E. 0 0.000E 698.50 0.
O.
3.60 0.000E-01 0.000E O
0.000E 722.20 0.
O.
1.90 0.000C-01 0.000E O
0.000E
(
783.70 0.
O.
15.00 0.000E-01 0.000E O
0 000E
(
I-132 FP 505.90 0.
O.
5.00 0.000E-01 0.000E O
0.000C
(
522.65 0.
O.
16.10 0.000E-01 0.000E O
0 000E 630.22 0.
O.
13.70 0.000E-01 0.000E O
0.000E
(
667.69 0.
O.
90.70*
0.000E-01 0.000E O
0.000E
(
671.60 0.
O.
5.20 0.000C-01 0.000C 0
0.000E 4
772.60 0.
O.
76.20 0 000E-01 0.000E O
0.000E 812.20 0.
O.
5.60 0.000C-01 0.000C 0
0.000E 954.55 0.
O.
18.10 0.000E-01 0.000E O
0.000E
(
1390.57 27, 13, 7.10 4.703E-01 1.966C 3
6.242E CS-134 FP 563.23 168.
77.
0.40 1.055E 00 1.030E
~6 1.252EL 569.32 263.
88.
15.40 1.045E 00 0.040E -7 8.287E
-E 404.70 1403.
157.
97.60
- 9. 906E -01 0.316C -7 2.711E -t 795.04 1040.
16.
85.40*
7.765E-01 0.570E -7 2.750E -f 801.93 107.
14.
0.70 7.714C-01 0.611C -7 1.107E -;
100.
85.108 9 147E-01 1.296E - 6 3.320E CC - 14 4 FP 00.12 40.
268.
1.60 2.321E 00 0.009C ~7 4.730C 133.53 0.
O.
10.00*
0.000E-01 0.000E O
0.000E
(
NATURAL PRODUCT 1 SIGMA NUCLIDE GDHR ENERGY AREA DKGND
%ABN
%EFF UCI / UNIT CRROR K-40 NP 1460.75 54.
16.
10.70*
4.529C-01 6 043E -7 1.412E -7 i
BI-214 NP 409.00 0.
O.
45.00*
0.000C-01 0.000E O
0.000E C
760.40 0.
O.
5.04 0.000E-01 0.000E O
0.000E i
934.10 0.
O.
3.21 0.000C-01 0.000E 0
0.000E 1120.00 0.
O.
14.90 Q1200E-01 0.000E 0
0.000E O
1230.00 0.
O.
5.92 0.000E-01 0.000E O
0.000E 1377.70 0.
O.
4.11 0 000E-01 0.000E 0
0.000E O
1400.00 0.
O.
2.49 0.000E-01 0.000C 0
0.000E C
~
1509.20 0.
O.
2.22 0.000E-01 0.000E O
0.000E O
1765.00 15.
O.
15.40 3'.'027E-01 1.375E ~7 6.285E -@
i 1
NUCLIDE IDENTIFICATION SYSTEM (REV 12/04)
NUCLIDC LINE ACTIVITY RCPORT PAGE 3
NATURAL PRODUCT 1 SIGM; NUCLIDC SDHR CNERGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR AC-228 NP 89.95 0.
O.
2.10 0.000E-01 0.000E O
0.000E 93.50 0.
O.
3.50 0.000E-01 0.000E O
0.000E 99.45 0.
O.
1 30 0.000E-01 0.000E O
0.000E 105.00 0.
O.
1.60 0.000C-01 0.000E O
0.000E 129.10 0.
O.
2.80 0.000E-01 0.000E O
0.000E 209.40 0.
O.
4.40 0.000E-01 0.000E O
0.000E 270.30 0.
O.
3.60 0.000E-01 0.000E O
0.000E 320.00 0.
O.
3.20 0.000E-01 0.000E. 0 0.000E 330.40 0.
O.
11.50 0.000E-01 0.000E O
0.000E 409.40 0.
O.
2.14 0.000E-01 0.000C 0
0.000E 463.00 0.
O.
4.00 0.000E-01 0.000E O
0.000E 755.20 0.
O.
1.04 0.000E-01 0.000E O
0.000E 772.10 0.
O.
1.56 0.000E-01 0.000E O
0.000E 794.80 1048.
16.
4.60 7.745C-01 1.591E -5 5.107E 911.07 0.
O.
27.80*
0.000E-01 0.000E O
0.000E 963.90 0.
O.
16.70 0.000C-01 0.000C 0
0.000E 1587.90 0.
O.
3.60 0.000E-01 0.000E O
0.000E 1630.40 0.
O.
1 87 0.000E-01 0.000C 0
0.000E TH-227 NP 50.20 0.
O.
9.15 0.000E-01 0.000E O
0.000C 79.80 60.
263.
2.10 2.321E 00 7.465E ~7 4.015C c
236.00 0.
O.
11.20*
0.000C-01 0.000C 0
0.000E 256.25 0.
O.
6.00 0.000E-01 0.000E O
0.000E 286.15 0.
O.
1 60 0.000E-01 0.000E O
0.000E 299.90 0.
O.
2.00 0.000E-01 0.000C 0
0.000E 304.44 0.
O.
1.05 0.000E-01 0.000E O
0.000E 329.80 0.
O.
2.00 0.000E 01 0.000E O
0.000E 334.40 0.
O.
1 00 0.000C-01 0 000E O
0.000E em
r
[
NUCLIDE IDENTIFICATION SYGTEM (REV 12/04)
{
UNKNOWN LINE REPORT PAGE 4
PK IT ENERGY AREA DKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR
%EF 2
3 74.42 170.
93.
1.02 140.07 142 23 3.40E-02 19.3 2.13E 3
3 76.40 108.
196.
2.24 152.82 142 23 2.16E-02 35.1 2.21E 14 0 1365.29 43.
10.
1.51 2730.32 2723 14 8.54E-03 20.6 4.01E -
LINES NOT MEETING
SUMMARY
CRITERIA PK NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED 1 W-187 72.06 2.390E 01H 0.505E O
2.704C -6 13.04%
ADN 4 CE-144 80.12 2.843E 02D 1.008E O
8.009E ~7 12.90%
ABN 4 TH-227 79.00 1.072E 01D 1.121C 0
7.465C -7 5.57%
ABN 5 AS-76 563.23 2.632E 01H 6.985E O
5.020E -5 2.04%
ADN 7 DR-02 606.30 3.530E 01H 4.260E O
2.073E
-4 0.37%
ABN 7 SD-127 603.50 3.850E 000 1.740E O
3.200E -5 4.05%
ADN 9 AC-220 794.00 1.913E 00Y 1.003E O
1.591E -5 4.73%
ABN 10 BR-04 002.20 3.180E 01M 7.337E 41 0.905E 35 8.02% DCY,ABN 11 NI-65 1115.53 2.520C 00H 6.526E 8
4.185E 2
34.50% DCY,ABN 13 MN-52 1333.00 5.670E 00D 1.456E O
2.207C -6 1.70%
ABN 15 I--132 1390.57 2.300C 00H 4.545E 9
1.966E 3
2.09% DCY,ABN 17 DI-214 1765.00 1.600E 03Y 1.000C 0
1.375E
-7 15.67%
ABN
=-g.
4 1
NUCLIDE IDENTIFICATION SYSTEM (REV 12/04)
SUMMARY
OF NUCLIDE ACTIVITY PAGE 5
TOTAL LINES IN SPECTRUM 17 LINES NOT LISTED IN LIBRARY 3
IDENTIFIED IN
SUMMARY
REPORT 11 64.71%
ACTIVATION PRODUCT 1-SIGMA NUCLIDE SDHR HALFLIFE DECAY UCI / UNIT ERROR
% ERR CD -60 AP 5.270E 00Y 1.001 7.730E -8 1.229E -0 41hi>&
ZN-65 AP 2.444C 02D 1.009 4,444E ~7 3.247C
-8
- 17. 5 2~
SB-122 AP 2.720E 00D 2.190
-2.475E -7 3.254C -0 42.i6 FISSION PRODUCT 1-SIGMA NUCLIDE SDHR HALFLIFE DECAY UCI / UNIT ERROR
% ERR CS -134 FP 2.060E 00Y 1.003 8.570E -7 2.750E -8 3.21 CS-137 FP 3.017C 01Y 1.000 1.296E
-6
- 3. 320E
--O 2.56 NATURAL PRODUCT t
1-SIGMA NUCLIDC SBilR HALFLIFC DECAY UCI / UNIT ERROR
% ERR K-40 NP 1.000E 03Y 1.000
-6r^'7r
.J 1.412E ~7
-2 3. 3 '-
1 No e
se
~
00-DEC-86 14:57:14 LIQUID SAMPLE HATCH PT-4 SN1295 SAMPLE DATE:
06 -DEC-86 07:00:00 SAMPLE IDENTIFICATION:
GN1295 TYPE OF SAMPLE:
LIQUID SAMPLE QUANTITY:
1000.000 UNITS:
ML' SAMPLE GEOMETRY:
SH-0 EFFICIENCY FILE NAME:
EFF2
.LMAR ACQUIRE DATE: 00-DEC-06 13:33:01
- FWHM(1332) 1.948 PRESET TIME (LIVE):
5000. SEC
- SENGITIVITY:
5.000 ELAPSED REAL TIME:
5000. SEC
- SHAPE PARAMETER : 10.0 %
ELAPSED LIVE TIME:
5000. SEC
- NDR ITERATIONS:
10.
DETECTOR: GE-2
- LIBRARY:NUCL. MASTER CALIB DATE:
00-DEC-06 13:22:25
- ENERGY TOLERANCE:
1.500KV KEV /CHNL:
0.4999252
- HALF LIFE RATIO:
0.00 0FFSET:
-0.0273409 KEV
- ADUNDANCE LIMIT:
80.00%
- 0. COEFF. :
4.575E-08 KEV /C**2
- t l
1 m-. g.
h e
t ENERGY WINDOW 24.97 TO 2048.43 PK IT ENERGY AREA DKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR fit 1
3 72.09 116.
26.
1.34 145.85 142 10 2 33E-02 16.6 1.40E 2
3 74.68 96.
50.
1.10 149.44 142 10 1.92E-02 20.5
)
3 3
76.77 93.
128.
1.48 153.41 142 18 1.06E-02 24.8 i
4 0
92.25 05.
267.
1.16 134.53 170 12 1.70E-C2 40.4 5
0 295.11 41.
132.
1.18 590.32 587 9 8 11E-03 55.0 6
0 352.54 90.
151.
0.91 705.20 702 11 1.01E-02 28.2 i
7 0
511.38 85.
120.
1.60 1022.83 1015 17 1.70E-02 31 9 8
0 567.42 147.
88.
6.80 1134.96 1124 22 2.95E-02 21.0 9
2 605.02 539.
40.
1.40 1210.15 1205 20 1.03E-01 4.9 1.13E:
10 2
609.40 82.
27.
1.29 1219.06 1205 20 1.64E-02 18.0
~
11 0
661.96 636.
40.
1.47 1324.02 1314 16 1.27E-01 4.4 12 0
796.18
- 346, 12.
1.51 1592.42 1587 12 6.92E-02 5.9 1
13 0.
002.19 64.
15.
1.45 1604.43 1599 12 1.2CE-02 18.1 14 0 1115.40 39.
51.
0.02 2230.74 2226 10 7.79E-03 40.7 i
15 0 1172.96 28.
21.
2.32 2345.02 2343 16 5 67E-03 42.5 16 0 1332.34 29.
7.
1.79 2665.40 2461 10 5 77E-03 20.4 17 0 1365.89 18.
O.
1 45 2731.56 2724 14 3.60E-03 23.4 10 0 1461.49 65.
O.
1 93 2922.69 2914 17 1.30E-02 15.5 i
PEAK GEARCH COMPLETED (REV 15.1)
WQ6 7
i
NUCLIDE IDENTIFICATION SYSTEM (REV 12/84)
NUCLIDE LINE ACTIVITY RCPORT PAGE 1
ACTIVATION PRODUCT 1 SIGM2 NUCL(DC GDHR CNCRGY ARCA BKGND
%ABN
%EFF UCI / UNIT CRROR N-13 AP 511.00 85.
128.
99.00*
1.149E 00 1 554E 92 4.959C 9 F-18 AP 511.00 05.
120.
96.00*
1.149E 00 5.097E 1
1.626C MN-S2 AP 744.20 0.
O.
85.00 0.000E-01 0.000C 0
0.000C 840.40 0.
O.
3.20 0.000C-01 0.000E O
0.000C 935.60 0.
O.
94.00 0.000C-01 0.000C 0
0.000E 1333.80 29.
7.
5.10 4.913C-01 0.241E ~7 2 344C 1434.40 0.
O.
100.00*
0.000E-01 0.000E O
- 21. 100.00 5.504C-01 2.706E -Q 1.184C -
1332.49 29.
7.
100.00*
4 913E-01 3.175E -0 9.030E -
ZN 65 AP 1115.52 39.
51.
50.75*
5.756E-01 7.259C -8 2.957E -
NI 65 AP 366.27 0.
O.
4.60 0.000C-01 0.000E O
0.000C 1115.53 39.
51.
14.00 5.756E-01 9.771E -1 3.900E -
1401.84 0.
O.
23.50*
0.000C-01 0.000C 0
0.000C W-107 AP 72.06 116.
26.
11.90 2.065E 00 1.272E -6 2 110E -
134.22 0.
O.
9.40 0.000C-01 0.000E O
0.000C g
479.55 0.
O.
23.40 0.000E-01 0.000E O
0.000E
{
551.55 O.
O.
5.40 0.000E-01 0.000E O
0.000C 610.37 0.
O.
6.70 0.000E-01 0.000E O
0.000E 685.81 0.
O.
29.20*
0.000C-01 0.000C 0
0 000E FIGGION PRODUCT 1 SIGMA NUCLIDC SDHR CNCRGY ARCA DKOND
%ABN
%CFF UCI / UNIT CRROR BR 02 FP 221.45 0.
O.
2 30 0.000E-01 0.000E O
0.000C i
554.32 0.
O.
70.60 0.000C-01 0.000E O
0.0000 606.30 539.
48.
1.20 9.905E-01 7.246C ~5 3 527C -
619.07 0.
O.
43.10 0.000E-01 0.000C 0
0.000C 698.33 0.
O.
27.90 0 000E-01 0.000E O
0.000E 774.49 0.
O.
03.408 0.000C-01 0.000C 0
0.000C 827.81 0.
O.
24.20 0.000E-01 0.000E O
0.000E 1007.57 0.
O.
1.30 0.000C-01 0.000C 0
0.000E 1043.97 0.
O.
27.40 0.000E-01 0.000E O
0.000E 1317.47 0.
O.
26.90 0.000E-01 0.000C 0
0.000E 1474.82 0.
O.
16.60 0.000E-01 0 000E O
0.000E BR-04 FP 902.20 64.
15.
6.10 7.714E-01 1 530C 25 2 767C 2 881 60 0.
O.
42.00*
0.000E-01 0.000C 0
0.000C 1015.90 0.
O.
6.20 0.000E-01 0.000E 0
0.000E i
1097.60 0.
O.
14.90 OIID0E-01 0.000E 0
0.000E a
RU-103 FP 497.00 0.
0.
86.40*
0.000E-01 0.000E O
0.000E 4
410.33 82.
27.
5 30 9 841E-01 0.863E ~7 1 597C CS-134 FP 563.23 0.
O.
8.40 0.*000E-01 0.000E O
0 000E e
569.32 0.
O.
15.40 0'.~000E-01 0.000C 0
0.000E 604 70 539.
48.
97.40 9 905E-01 3.018E -7 1.469E -
795.84 346.
12.
85.40*
7.765E-01 2 026C ~7 1 650E 801.93 44.
15.
0.70 7.714E-01 5.148E - 7 9.309E -:
CG-137 FP 661.44 636.
40.
05.10*
9.147E-01 4.410E -7 1.950E 2.015E-f ND-147 FP 91.10 85.
267.
27.90*
2 731C 00 6.976E -8 319.41 0.
O.
2.00 0.000C-01 0.000E O
0 000E Q
439.90 0,
0.
1.20 0.000E-01 0.000E 0
0.000E Q
531.02 0.
O.
13.10 0.000C-01 0.000E O
0.000E d
j
t NATURAL PRODUCT l
1 SIGW NUCLIDC GDHR ENERGY AREA BKGND
%ABN
%EFF UCI / UNIT ERROR K-40 NP 14d0.75 65.
O.
10.70*
4.527E-01 7.254E ~7 1.122E NUCLIDC IDENTIFICATION SYSTEM (REV 12/84)
NUCL1DE LINE ACTIVITY REPORT PAGE 2
NATURAL PRODUCT 1 SIGMQ NUCLTDE SBHR ENCRGY AREA BKGND
%ABN
%EFF UCI / UNIT ERROR T L-200 NP 277.35 O.
O.
6.00 0.000E-01 0.000E O
0.000E 510.80 05.
120.
21.60 1 149E 00 1.057C -7 5.725E c 583.14 0.
O.
85.80*
0.000E-01 0.000E O
0 000E 763.13 0.
O.
1.64 0.000C-01 0.000E 0.0.000E 860.37 0.
O.
12.00 0.000E-01 0.000E O
0 000E BI-214 NP 409.00 02.
27.
45.00*
9.841C-01 1.002C -7 1.806E d 760.40 0.
O.
5.04 0.000E-01 0 000E O
0 000E 934 10 0.
O.
3.21 0.000E-01 0.000E O
0.000E 1120.00 0.
O.
14.90 0.000E-01 0.000E O
0.000E 1230.00 0.
O.
5.92 0.000C-01 0.000E O
0.000E 1377.70 0.
O.
4.11 0.000E-01 0.000E O
0.000E 1400.00 0.
O.
2.49 0.000C-01 0.000E o
0.000E 1509.20 0.
O.
2.22 0.000E-01 0.000E O
0.000E 1765.00 0.
O.
15.40 0.000C-01 0.000E O
0.000E PB-214 NP 241.91 0.
O.
7.50 0.000E-01 0.000E O
0.000E 293 20 41.
132.
10.60 1.050E 00 6.374C 0
3,503E c 351.90 90.
151.
35.00*
1 590E 00 8.579E -8 2.4206 c
AC-220 NP UV.95 0.
O.
2.10 0.000C-01 0.000C 0
0.000E 93.50 85.
267.
3.50 2.731E 00 4.025E -7 1.947E -
97.45 0.
O.
1.30 0.000C-01 0.000E O
0.000E 105 00 0.
O.
1 60 0.000E-01 0.000E O
0.000E 129.10 0.
O.
2 00 0.000C-01 0.000E O
0.000E 209.40 0.
O.
4.40 0.000E-01 0.000E O
0.000E 270.30 0.
O.
3.60 0.000E-01 0.000C 0
0.000E 328.00 0.
O.
3.20 0.000C-01 0.000E O
0.000E 330.40 0.
O.
11 50 0.000C-01 0.000C 0
0.000E 409.40 0.
O.
2.14 0.000E-01 0.000E O
0.000E 463.00 0.
O.
4.00 0.000C-01 0.000C 0
0.000E 755.20 C.
O.
1.06 0.000C-01 0.000E O
0.000E 772.10 0.
O.
1 56 0.000C-01 0.000C 0
0.000E 794.00 346.
12.
4.60 7.765E-01 5.240E -6 3.079E e 911 07 0.
O.
27.0**
0.000C-01 0.000E O
0.000E 968.90 0.
O.
16.70 0.000E-01 0.000E 0
0 000E 1507.90 0.
O.
3.60 0.000C-01 0.000C 0
0.000E 1630.40 0.
O.
1 87 0.000E-01 0.000E 0
0.000E U-230 NP 43.30 0.
0.
3.90*
0.000C-01 0.000E 0
0.000E 93 00 85.
267.
5 60 2 731E 00 3 009E ~7 1 214E o
1001.00 0.
0.
0.59 0ag00E-01 0 000E 0
0 000E AN-511 NP 511.01 05.
128. 100 00*
1.149E 00 4.002E -0 1.277E -
es
NUCLIDE IDENTIFICATION SYSTEM (REV 12/04)
UNKNOWN LINE REPORT PAGE 3
PK IT ENERGY AREA BKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR
%EF 2
3 74.68 76.
50.
1.18 149.44 142 10 1.92C-02 20 5 2 14E 3
3 76.77 93.
128.
1.48 153.61 142 18 1 06E-02 24.0 2.23E 8
0 567.42 147.
88.
6.80 1134.96 1124 22 2.95E-02 21.0 1.05E 17 0 1365.89 18.
O.
1.45 2731 56 2724 14 3.60E-03 23.6 4.81E-LINEG NOT MEETING
SUMMARY
CRITERIA PK NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ADHDIFF FAILED 1 W-187 72.06 2.390E 01H 4.964E O
1.272E -6 13.04%
ABN 4 ND-147 91.10 1.106E 01D 1.155E O
6.976E -0 63.12%
ABN 4 AC-228 93.50 1.913E 00Y 1.002E O
4.025E -7 0.32%
ABN 4 U-238 93.00 9.999E 03Y 1.000E O
3 009E -7 55.51%
ABN 7 N-13 511.00 9.970E 00M 3.876E 99 1 554E 92 100.00%
DCY 7 F - 18 511.00 1.097E 02M 1.233E 9
5.097E 1
100.00%
DCY 7 TL-200 510.00 1.913E 00Y 1.002E O
1 057E
-7 16.90%
ABN 9 BR-02 606.30 3.530E 01H 2.959E O
7.244E -5 0.37%
ABN 10 RU-103 410.33 3.935E 01D 1.041E O
8 043E -7 5.70%
ABN 10 D I -214 609.00 1.600E 03Y 1.000E O
1.002E -7 45.78%
ADN 12 AC-228 794.00 1.913E 00Y 1 002E O
5 240E -6 0.32%
ABN 13 DR-84 002.20 3.100E 01M 2.000E 31 1.530E 25 0.02% DCYeABN 14 NI-65 1115.53 2.520E 00H 3.951E 6
9.771E -1 34.50% DCY,ABN 16 MN-52 1333.30 5.670E 00D 1.325E O
0.241E -7 1.70%
ABN S e
i NUCLIDE IDENTIFICATION SYSTEM (REV 12/84) i
SUMMARY
OF NUCLIDC ACTIVITY PAGC 4
TOTAL LINES IN SPECTRUM 18 LINC!i NOT LIGTED IN LIBRARY 4
IDENTIFIED IN
SUMMARY
REPORT 11 61.11%
ACTIVATION PRODUCT 1-SIGMA NUCLIDC GBHR HALFLIFC DCCAY UCI / UNIT ERROR
% ERR CC 00 AP 5.270E 00Y 1.001 3 175E -8 9.030E -9 20.44 14 AP 2.444C 020 1.007 7.259C -0 2.957E -8 40.73 FIGGION PRODUCT 1-SIGMA NUCLIDC GBHR Hall'LIFC DCCAY UCI / UNIT ERROR
% ERR CS-134 FP 2.060E 00Y 1.002 2.826E ~7 1.658E -8 5.87 CS-137 FP 3.017E 01Y 1.000 4.418C -7 1.950E -8 4.41 NATURAL PRODUCT 1-GIGMA NUCLI Dt:
GDHR HALFLIFC DECAY UCI / UNIT CRROR
%CRR K-40 NP 1.000E 03Y 1.000 7.254E ~7 1.122C -7 15.47 PB-214 NP 1.600C 03Y 1.000 8.579C -8 2.420E -3 20.20 AN-511 NP 1 000C 03Y 1.000 4.002C
-8 1 277E -0 31.90 l
M*
em 9
l
00-DCC-86 09:55:11 LIQUID SAMPLC HATCH PT-A SAMPLC DATE:
06-DEC-86 07:00:00 SAMPLC IDCNTIFICATION:
GN1293 TYPC OF SAMPLC:
LIQUID SAMPLC QUANTITY:
1000.000 UNITS:
CC SAMPLC GEONETRY:
SH-0 EFFICIENCY FILE NANC:
CFF2
.LMAR ACQUIRC DATC: 00-DCC-06 08:30:50
- FWHM(1332) 1.748 PRESCT TIME (LIVE):
5000. SCC
- SENSITIVITY:
5.000 ELAPSCD RCAL TIME:
5000. SCC
- SHAPC PARAMETER : 10.0 %
ELAPSED LIVE TIME:
5000. SCC
- NDR ITERATIONS:
10.
DCTCCTOR: GC-2
- LIDRARY:NUCL.NASTER CALID DATE:
08-DEC-06 00:23:40
- CNCROY TOLERANCE:
1.500KV NEV/CHNL:
0.4999174
- HALF LIFE RATIO:
0.00 0FFSCT:
-0.0314367 KEV
- ADUNDANCE LIMIT:
80.00%
0.
COtfr.
4.442C-03 KEV /C**2
- me-p o l
l I
ENERGY WINDOW 24.96 TO 2048.38 PK IT ENCRGY AREA DKGND FWHM CHANNCL LEFT PW CTS /SEC % ERR FIT' 1
3 72.69 96.
13.
1 29 145.47 142 38 1.92E-02 20.9 3 94E (
2 3
74.44 159.
46.
1.74 140.96 142 30 3.18E-02 17.4 3
3 76.98 120.
91.
1.92 154.04 142 30 2.55E-02 23.2 4
3 79.08 93.
124.
1.96 153.24 142 30 1.07E-02 30 7 5
3 81 24 67.
145.
1.86 162.56 142 38 1.34E-02 39.5 6
3 83.27 58.
173.
1.79 166.63 142 30 1.14E-02 46.0 7
3 05.02 57.
164.
1.53 170.13 142 30 1.15C-02 40.5 8
3 87.28 51.
166.
1.41 174.64 142 38 1.03E-02 41.6 9
0 92.48 79.
314.
0.75 105.06 101 10 1.59E-02 42.4 10 0
176.64 90.
274.
1.06 353.39 349 10 1.80E-02 37.3 11 0
420.30 148.
125.
1.39 056.73 052 12 2.96E-02 19.7 12 0
563 60 68.
97.
1.81 1127.34 1122 13 1.37E-02 32.5 13 0
569.65 122.
57.
1.22 1139.43 1134 9 2.44E-02 14.2 14 0
604.92 701.
143.
1 32 1209.97 1205 12 1.40E-01 5.3 15 0
661.04 937.
94.
1.54 1323.01 1316 17 1.87E-01 4.0 16 0
794.04 573.
37.
1.39 1592 10 1507 12 1.15E-01 4.8 17 0
003.47 91.
39.
0.90 1607.03 1600 17 1.01E-02 20.0 10 0 1115.86 218.
27.
1.60 2231.72 2226 14 4.37E-02 8.8 19 0 1173.49 153.
36.
1.16 2346.95 2341 12 3.06E-02 10.9 20 0 1332.80 162.
12.
1.09 2665.48 2659 12 3.23E-02 9.3 21 0 1345.52 20.
O.
3.00 2730.90 2725 13 4.00E-03 22.4 22 0 1460.80 61.
O.
1.41 2921.39 2913 16 1.22E-02 14.4 PCAK SCARCH COMPLETCD (RCV 15.1) as
I.
NUCLIDE IDENTIFICATION CYSTEM (REV 12/84)
NUCLIDE LINE ACTIVITY REPORT PAGE 1
FISSION GAS 1 SIGMQ i
NUCLIDC SDHR ENERGY AREA BKGND
%ABN
%EFF UCI / UNIT CRROR<
l XE-133 FG 01 00 67.
145.
36.50*
2.398E 00 5.450E -8 2.152E e
{
ACTIVATION PRODUCT l
1 SIGMQ i
NUCLIDC SBHR ENCRGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR MN-52 AP 744.20 0.
O.
05.00 0.000E-01 0.000E O
0.000E 840.40 0.
O.
3.20 0.000E-01 0 000E O
0.000E 935.40 0.
O.
94.00 0.000E-01 0.000E O
0.000E 1333.80 162.
12.
5.10 4.913E-01 4.501E -6 4 207E -
l 1434.40 0.
O.
100.00*
0.000E-01 0.000E O
0.000E i
- 36. 100.00 5.502E-01 1.504E -7 1.642C
?
1332.49 162.
- 12. 100.00*
4.913E-01 1.779E -7 1.662E -
I ZN-65 AP 1115.52 218.
27.
50.75*
5.754E-01 4.065E ~7 3.570E -
l NI-45 AP 366.27 0.
O.
4.60 0.000E-01 0.000E O
0.000E 1115.53 218.
27.
14.30 5.754E-01 1.371E O
1.204E -
j; 1481.84 0.
O.
23.50*
0.000E-01 0 000E 0
0.000E
}
AS-76 AP 559.10 0.
O.
44.70*
0.000E-01 0.000E 0
0.000C j
563.23 68.
97.
1.20 1 055E 00 1.096E -5 3.556C -
i 657.03 0.
O.
6.10 0 000E-01 0.000E O
0.000E i
1212.72 0.
O.
1.60
- 0. 000E- 01 0.000E 0
0.000E 1216.02 0.
O.
3.30 0.000E-01 0.000E 0
0.000E l
1228 52 0.
O.
1.40 0.000E-01 0.000E O
144.
3 72*
2.597E 00 2.085E ~7 1.201E -
j SB-122 AP 563.93 68.
97.
70.608 1.055E 00 8.459E -8 2.746E j
BA-133 Ar 01.00 47.
145.
35.55 2.390C 00 4.245C ~3 1.676C -
l 276.40 0.
O.
6.90 0.000E-01 0.000E 0
0.000E
~
302.80 0.
O.
17.80 0.000E-01 0.000E O
0.000E l
356.00 0.
O.
62.40*
0.000E-01 0.000E 0
0.000E 333.80 0.
O.
8.70 0.000E-01 0.000E 0
0.000E TA-102 AP 84.68 57.
164.
2.70 2.527E 00 4.604E -7 1.865E -
100.11 0.
O.
14 00 0.000E-01 0 000E O
0.000C l
113.67 0.
O.
1.90 0.000E-01 0.000E O
0 000E 152.43 0.
O.
7 20 0.000C-01 0.000E 0
0.000E
(
i 156.38 0.
O.
2.70 0.000E-01 0 000E 0
0.000E 179.39 0.
0.
3.10 0.000E-01 0.000E 0
0.000E 190.35 0.
O.
1.50 0.000E-01 0 000E 0
0 000E 222.10 0.
O.
7.50 0.000E-01 0.000E 0
0.000E 229.32 0.
O.
3.60 0II00E-01 0.000E 0
0.000E 264.07 0.
0.
3.60 0 000E-01 0.000E 0
0.000E l
1001.68 0.
O.
2.10 0.000E-01 0.000E 0
0.000E 1121.28 0.
O.
34 90*
0.*000E-01 0.000E 0
0.000C 1109.04 0.
O.
16.40 0'.~000E-01 0.000E 0
0.000E 1221.41 0.
O.
27.30 0.000E-01 0.000E 0
0.000E 1230.97 0.
O.
11.40 0.000E-01 0 000E O
0 000E i
1257.47 0.
0.
1 50 0.000E-01 0 000E O
0.000C 1209 17 0.
O.
1.40 0.000E-01 0.000E 0
0.000E
NUCLIDE IDENTIFICATION SYSTEM (REV 12/34)
NUCLIDE LINE ACTIVITY REPORT PAGE 2
ACTIVATION PRODUCT 1 SIGMC NUCLIDE SBHR ENERGY AREA BKGND
%ABN
%EFF UCI /U:4IT ERROR W-107 AP 72.06 96.
13.
11.90 2.056E 00 9.039E -7 1.900E e 134.22 0.
O.
9.40 0.000E-01 0.000E O
0.000E 479.55 O.
O.
23.40 0.000C-01 0.000E O
0.000E 551.55 O.
O.
5.40 0.000E-01 0.000E O
0.000E 410.37 0.
O.
6.70 0.000E-01 0.000E 0
0.000C 685.01 0.
O.
29.20*
0.000E-01 0.000E O
0.000E FISSION PRODUCT 1 SIGM2 NUCLIDE SDilR ENERGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR BR-02 FP 221.45 0.
O.
2.30 0.000E-01 0.000E O
0.000E 554.32 0.
O.
70.60 0.000E-01 0.000E O
0.000E 606.30 701.
163.
1.20 9.906E-01 C.544E -5 4.537E -
619.07 0.
O.
43.10 0.000E-01 0.000E 0
0.000C 698.33 0.
O.
27.90 0.000E-01 0.000E O
0.000E 776.49 0.
O.
03.40*
0.000C-01 0.000C 0
0.000C 827.81 0.
O.
24.20 0.000E-01 0.000E O
0.000E 1007.57 0.
O.
1.30 0.000E-01 0.000C 0
0.000E 1043.97 0.
O.
27.40 0.000E 01 0.000E O
0.000E 1317.47 0.
O.
26.90 0.000C-01 0.000E O
0.000E 1474.02 0.
O.
16.60 0 000E-01 0.000E O
0.000E BR-04 FP 002.20 91.
39.
6.10 7.703C-01 3.011E 22 6.022E 2, 881.60 0.
O.
42.00*
0.000E-01 0.000E O
0 000E 1015.90 0.
O.
6.20 0.000E-01 0.000C 0
0.000C 1897.60 0.
O.
14.90 0.000E-01 0.000E 0
0.000E SB-125 FP 176.33 90.
274.
6.89 2.711E 00 2.607E ~7 7.727E -
427.90 148.
125.
29.33*
1.343E 00 2.032E -7 4.005E -l 443.40 0.
O.
10.35 0.000C-01 0.000E O
0.000E i
600.60 0.
O.
17.00 0.000E 01 0.000E O
0 000E 636.00 0.
O.
11.30 0.000C-01 0.000C 0
0.000E SB-127 FP 252.40 0.
O.
8.50 0 000E-01 0.000E O
0 000E 270.80 0.
O.
2.00 0.000E-01 0 000E O
0.000E 412.10 0.
O.
3.80 0.000E-01 0.000E 0
0.000E 445.10 0.
0.
4.30 0.000E-01 0.000E 0
0 000C 0.g 473.00 O.
25.70 0.000E-01 0.000E O
0.000E 543.30 0.
O.
2 90 0.000E-01 0.000E 0
0.000E 603.50 701.
163.
4.40 9.906E-01 1.267C -5 4 729E -
605.70 0.
O.
36.60*
OII00E-01 0.000E O
0.000E 690.50 0.
O.
3.60 0.000E-01 0.000E 0
0.000E 722.20 0.
O.
1.90 0.000E-01 0.000E O
0.000E 783.70 0.
O.
15.00 0.*000E-01 0.000E O
0 000E 4
NUCLIDE IDCNTIFICATION SYSTEM (RCV 12/84)
NUCLIDE LINE ACTIVITY REPORT PAGE 3
FISSION PRODUCT 1 SIGMA NUCLIDC SDHR ENCRGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR TE-131M FP 81.14 67.
145.
4.10 2.398E 00 1.174E -6 4.634E -
102.06 0.
O.
8.00 0.000C-01 0.000E O
0.000C 149.71 0.
O.
5.10 0.000E-01 0 000E O
0.000E 200.63 0.
O.
7.40 0.000E-01 0.000E O
0.000E 240.93 0.
O.
7.80 0.000E-01 0.000E O
0 000E 270.56 0.
O.
1.00 0.000E-01 0.000E 0
0.000C 334.27 0.
O.
9.70 0.000E-01 0.000E O
0.000E 364.98 0.
O.
1.20 0.000E-01 0.000E O
0.000C
(
452.30 0.
O.
1 60 0.000E-01 0.000E O
0.000E 462.92 0.
O.
1.00 0.000E-01 0.000E O
0.000C
(
586.30 0.
O.
2.00 0.000E-01 0.000E O
0.000E
?
665.05 0.
O.
4.40 0.000E-01 0.000E O
0 000E 713.10 0.
O.
1.50 0.000E-01 0.000E O
0 000E 4
744.20 0.
O.
1.60 0.000E-01 0.000E O
0.000C 773.67 0.
O.
38.40*
0.000E-01 0.000E O
0.000E 702.49 0.
O.
7.90 0.000C-01 0.000E 0
0.000E d
793.75 0.
O.
14.00 0.000E-01 0.000E 0
0 000E 022.78 0.
O.
6.20 0.000E-01 0.000C 0
0.000E q
852 21 0.
O.
20.90 0.000E-01 0.000E O
0.000E 910.00 0.
O.
3.30 0.000E-01 0.000E O
0.000C 920.62 0.
O.
1.20 0.000E-01 0.000E O
0.000E 1059.69 0.
O.
1.60 0.000C-01 0.000E o
0.000E 1125.46 0.
O.
11.50 0.000E-01 0.000E O
0.000E 1143.80 0.
O.
1.50 0.000E-01 0.000C 0
0.000C i
1206.40 0.
O.
9.90 0.000E-01 0.000E O
0.000E t
1646.01 0.
O.
1.20 0.000E-01 0.000E O
0.000C 1807.70 0.
O.
1.40 0.000E-01 0.000E O
0.000E 5
2000.94 0.
O.
2.00 0.000E-01 0.000E O
0 000E d
CS-134 FP 563.23 68.
97.
3.40 1.05SC 00 4.100C -7 1.357E -:
569.32 122.
57.
15.40 1.045E 00 4.102E -7 5.035E 4 604.70 701.
163.
97.60 9.906E-01 3.927E ~7 2.005C -0 795.84 573.
37.
85.40*
7.766E-01 4.681C -7 2.256E -
801.93 0.
O.
8.70 0.000E-01 0.000E 0
0.000C d
CS-136 FP 46.91 0.
O.
12.50 0.000E-01 Ot000E O
0.000E d
86.29 51.
166.
6.30 2.577E 00 1.897E -7 7.879E -
153.22 0.
O.
7.50 0 000E-01 0.000E 0
0.000E 176.56 90.
274.
13.60 2.711E 00 1.473E ~7 5.477E -
273.65 0.
O.
12.70 0.000E-01 0.000E 0
0.000E 340.57 0.
O.
48.50 OII00E-01 0.000E 0
0.000E 810.50 0.
O.
99.70 0.000E-01 0.000E O
0.000E 1040.07 0.
O.
77.00*
0.000E-01 0.000E 0
0.000C C
1235 34 0.
O.
19.70 0.*0 00 E-01 0.000E 0
0.000E
(
94.
05 10*
7.~148E-01 4.503E ~7 2.624E -$
CE-144 FP 80.12 93.
124.
1.60 2.318E 00 1.347E -6 4 195E ~%
133.53 0.
O.
10.80*
0.000E-01 0.000E O
314.
27.90*
2.737E 00 6.405E -0 2 714E ~@
319.41 0.
O.
2.00 0.000E-01 0.000E O
0.000E d
439.90 0.
O.
1.20 0.000E-01 0.000E 0
0.000C 531.02 0.
O.
13 10 0.000E-01 0.000E 0
0.000E d
EU-155 FP 86.50 51.
164.
30.00*
2.597E 00 3.476E -8 1.448E -d 105.30 0.
O.
20.50 0.000E-01 0.000E o
0.000E d
NATURAL PRODUCT 1 SIGMA)
NUCLIDE SBHR ENERCY AREA BKGND
%ABN
%EFF UCI / UNIT ERROR l K-40 NP 1460.73 61.
O.
10.70*
4.529C-01 6.005C -7 9.709C NUCLIDE IDENTIFICATION SYSTEM (REV 12/04)
NUCLIDC LINE ACTIVITY REPORT PAGE 4
NATURAL PRODUCT 1 SIGMA NUCLIDE SBHR ENERGY AREA BKGND
%ABN
%CFF UCI / UNIT CRROR AC-220 NP 89.95 0.
O.
2 10 0.000E-01 0.000E 0
0.000E 93.50 79.
314.
3.50 2.737C 00 4.430E ~7 1.901E -
99.45 0.
O.
1.30 0.000E-01 0.000E O
0.000C 105.00 0.
O.
1.60 0.000C-01 0.000E O
0.000E 129.10 0.
O.
2.00 0.000E-01 0.000E O
0.000E 209.40 0.
O.
4.40 0.000E-01 0.000C 0
0.000C 270.30 0.
O.
3.60 0.000E-01 0 000E O
0.000E 320.00 0.
O.
3.20 0.000C-01 0.000E O
0.000C 338.40 0.
O.
11.50 0.000E-01 0.000E O
0.000E 409.40 0.
O.
2.14 0.000C-01 0.000E O
0.000C 463.00 0.
O.
4.00 0.000E-01 0.000E O
0.000C 755.20 0.
O.
1.06 0.000E-01 0.000E O
0.000E i
772.10 0.
O.
1.56 0.000E-01 0.000E O
0 000C i
794.80 573.
37.
4.60 7.766E-01 0.691C -6 4 100E -
911.07 0.
O.
27.808 0.000E-01 0.000E O
0.000E 960.90 0.
O.
16.70 0.000C-01 0.000E O
0.000C a
1507.90 0.
O.
3.60 0.000E-01 0.000E O
0.000E 1630.40 0.
O.
1.07 0.000C-01 0.000E O
0.000C TH 227 NP 50.20 0.
O.
9.15 0.000E-01 0.000E O
0 000E 79.80 93.
124.
2.10 2.31HC 00 1.119C ~6 3.436E 236.00 0.
O.
11.20*
0.000C-01 0.000E O
0.000E 256.25 0.
O.
6.30 0.000C-01 0.000C 0
0.000C 286.15 0.
0.
1.60 0.000E-01 0.0000 0
0.000E 299.90 0.
O.
2.00 0.000E-01 0.000E O
0.000C 4
304.44 0.
O.
1.05 0.000E-01 0 0000 0
0.000E 4
329.80 0.
O.
2.00 0.000C-01 0.000E O
0.000E q
334.40 0.
O.
1.00 0.000E-01 0.000E O
0.0000 U-238 NP 63.30 0.
O.
3.90*
0.000E-01 0.000E 0
0 000E 93.00 79.
314.
5.60 2.737E 00 2.799C ~7 1.104E -
2001.00 0.
O.
0.59 0.000E-01 0.000E O
0 000C Ne l
NUCLIDC IDENTIFICATION SYSTEM (REV 12/04)
UNKNOWN LINE RCPORT PAGE 5
PK IT CNCRGY ARCA DKGND FWHM CHANNCL LCFT PW CTS / SCC % ERR
%CF 2
3 74.44 159.
46.
1.76 148.96 142 30 3.10C-02 17.4 2.13C 3
3 76.98 128.
91.
1.92 154.04 142 30 2.55E-02 23.2 2 24C 6
3 83.27 58.
173.
1 79 166.43 142 30 1 14E-02 46.0 2.47C 21 0 1345.50 20.
O.
3.00 2730.90 2725 13 4.00E-03 22.4 4.81E-LINES NOT MCETING GUMMARY CRITCRIA PN NUCLIDE ENERGY HALFLIFC DECAY UCI / UNIT ABNDIFF FAILCD 1 W-187 72.06 2.390C 01H 4.209E O
9.089C -7 13.04%
ABN 4 CC-144 80.12 2.043C 02D 1.005E O
1.367C -6 12.90%
ABN 4 TH-227 79.80 1.072C 01D 1.001C 0
1 119C -6 5.57%
ABN 5 TC-131M 81.14 3.000E 01H 3.190E O
1 174C -6 2.29%
ABN 5 BA-133 01.00 1.070C 01Y 1.000C 0
4.245C -0 27.07%
ABN 7 TA-182 84.60 1.150E 02D 1.013E O
4.604C -7 1 89%
ABN 8 CS-136 04.29 1.310E 01D 1.117C 0
1 097C -7 6.63%
ABN 8 CU-155 86.50 4.960E 00Y 1.001E O
3.476E -8 60.04%
ABN 9 ND-147 91 10
-1.106E 01D 1.140C 0
6.405E -8 63.12%
ABN 9 AC-228 93.50 1.913C 00Y 1.002C 0
4.400C -7 8.32%
ABN 9 U-238 93.00 9.999E 03Y 1.000E O
2.799C ~7 55.51%
ABN 10 GB-125 176.33 2.770C 00Y 1.001C 0
2.607C -7 47.07%
ABN 10 CC-136 176.56 1.310E 01D 1.117C 0
1.473E -7 6.63%
ADN 11 GD 125 427.90 2.770C 00Y 1.001C 0
2.032C ~7 47.07%
ABN 12 AS-76 563 23 2.632E 01H 3.752E O
1.096E ~5 2.04%
ADN 14 BR-02 606.30 3 530C 01H 2.680C 0
8 544E -5 0.37%
ABN 14 GB-127 603.50 3.050C OOD 1.457C 0
1 267C -5 4.05%
ABN 16 AC-220 794.00 1.913E 00Y 1 002C 0
0.691E -6 0.32%
ADN 17 BR-84 802.20 3.180C 01M 2.007C 20 3.011E 22 8.82% DCY,ABN 18 NI-65 1115.53 2.520E 00H 9.893C 5
1.371C 0
34 50% DCYrABN 20 HN-52 1333.00 5.670E 00D 1.291C 0
4.501E -6 1.70%
ABN i
1
\\
U NUCLIDE IDENTIFICATION SYSTEM (REV 12/84)
SUMMARY
OF NUCLIDC ACTIVITY PAGE 6
TOTAL LINES IN SPECTRUM 22 LINCS NOT LISTED IN LIBRARY 4
IDENTIFIED IN
SUMMARY
REPORT 12 54.55%
FISSION OAS 1-SIGMA NUCLIDC SDHR HALFLIFE DCCAY UCI / UNIT CRROR
%CRR r5-133 FG 5.240E 00D 1.319 5.450C -0 2.152C -8 ac.an ACTIVATION PRODUCT 1-SIGMA NUCLIDC SDHR HALFl.IFC DECAY UCI / UNIT CRROR
% ERR CD-60 AP 5.270E 00Y 1.001 1.779C -7 1.662E -8 9.35 ZN-65 AP 2.444C 02D 1.006 4.065E ~7 3.570C -0 0.78 CD iG%
AP 4.530E 02D 1.003,g.on55 -7 1.201E -7 SS
S AP 2.720C 00D 1.704
- 0. '" ?C - 0 2.746E -8
_12.A6 FISSION PRODUCT 1-SIGMA NUCLIDC 3DHR HALFLIFC DECAY UCI / UNIT CRROR
% ERR CS-134 FP 2.060E 00Y 1.002 4.681E -7 2.256E -0 4 02 CS-137 FP 3.017C 01Y 1.000 6.503C -7 2.624E -8 4.03 NATURAL PRODUCT 1-SIGMA NUCLIDC SDHR HALFLIFC DECAY UCI / UNIT CRROR
%CRR K-40 NP 1.000E 03Y 1.000 4.805E -7 9.709E -0 14.39
00-DEC-36 11:37:28 LIQUID SAMPLE HATCH PT-B SN1294 SAMPLE DATE:
06-DEC-86 07:00:00 l
SAMPLC IDENTIFICATION:
GN1294 TYPE OF SAMPLE:
LIQUID SAMPLC QUANTITY:
1000.000 UNITS!
CC SAMPLE GEOMETRY:
SH-0 EFFICIENCY FILC NAMC:
EFF2
.LMAR ACQUIRC DATE: 00-DEC-06 10:15:15
- FWHH(1332) 1.948 PRESET TIME (LIVE):
5000. SEC
- SENSITIVITY:
5.000 ELAPSED RCAL TIME:
5000. SEC
- SHAPE PARAMETER : 10.0 %
ELAPSED LIVE TIME:
5000. SEC
- NBR ITERATIONS:
10.
DETCCTOR: GC 2
- LIBRARY NUCL. MASTER CALID DATCt 00-DEC-06 08:23:40
- ENERGY TOLERANCE:
1.500KV KEV /CHNL:
0.4999174
- HALF LIFE RATIO:
0.00 0FFSCT:
-0.0314367 KEV
- ABUNDANCE LIMIT:
80.00%
0.
COCFF.
4.442C-00 KEV /C**2 *
-g.
46
. ' gy. g
t IGY WINDOW 24.96 TO 2040.38 I
BKGND FWHM CHANNEL LEFT PW CTS /SEC XERR FIT ggggg 13.
1 28 145 62 142 18 1 15E-02 25.8 6 22E 00%EFF UCI / UNIT ERROR 32.
1.35 149.27 142 10 1 53E-02 21.7 49E 00 1.800E 86 3 357E @
64.
1.41 154.39 142 10 1 08E-02 29.5 49E 00 1.584E 1
2.953E 106.
1.24 185.17 183 8 1 28E-02 32.5 59E 00 5.723E -7 1.476E -
44.
2.34 591.60 588 9 9 87E-03 29.7
'00E-01 0.000 0
C.000 38.
0.81 703.66 701 0 0 29E-03 31.5 o,
0E 28.
2.31 1022.60 1015 16 1 35E-02 18.4 300E-01 0.000E 0
0.000E 14.
1.14 1210 80 1216 0 1 41E-02 14.1
>00E-01 0.000E 0
0.000E 4.
1.44 2721.87 2915 15 1 24E-02 14.8
)00C-01 0.000E 0
0.000C 5.
1.17 3530.80 3525 12 3.78E-03 34.3 GCARCH COMPLETED (REV 15.1) 1 SIGMA
%EFF UCI / UNIT ERROR 000E-01 0.000E 0
0 000E 042C-01 7.571E ~7 1.223C -
000E-01 0.000E 0
0 000E 000E-01 0.000C 0.4.000C 593E 00 1.269E ~6 4.003E -
000C-01 0.000E 0
0 000E 000E-01 0.000E 0
0 000E 000C-01 0.000C 0
0.000E 000E-01 0.000E 0
0.000E 730C 00 5.197E -8 1.680C 000E-01 0.000E O
0 000E 000E-01 0.000E 0
0.000E 000E-01 0.000C 0
0.000C 1 SIGMA
%EFF UCI / UNIT CRROR
.528E-01 6.922E -7 1.160E -
.000E-01 0.000E 0
0.000E
.149E 00 2.013E ~7 3 754E -
.000C-01 0.000E 0
0.000E
.000E-01 0.000E 0
0.000E
.000E-01 0.000E O
0.000E
.842E-01 8 606E -8 1.386E -
7T00E-01 0.000E 0
0 000E
.000E-01 0 000C 0
0.000C
.000E-01 0.000E O
0.000C
- .000E-01 0.000E 0
0 000E
'.*000E-01 0.000E 0
0.000E
'.000E-01 0 000E 0
0 000E s.000E-01 0.000E O
0.000E I.826E-01 1 735E -7 5.945E ~
).000E-01 0.000E O
0 000E
. 846E 00 7 771C -8 2 305E -
L.593E 00 3 929E -8 1.239E -:
I NUCLIDE IDENTIFICATION SYSTEM (REV 12/04)
NUCL(DC LINC ACTIVITY REPORT PAGE 2
NATURAL PRODUCT 1 SIGMd NUCLIDC SBHR ENERGY AREA DKGND
%ABN
%EFF UCI / UNIT ERROR AC-228 NP 89.95 O.
O.
2.10 0.000E-01 0.000E 0
0.000E 93.50 64.
106.
3.50 2.730E 00 3.425E ~7 1.177E c 99.45 0.
O.
1.30 0.000E-01' O.000E O
0.000E 105.00 0.
O.
1.60 0 000E-01 0.000E O
0.000E 129.10 0.
O.
2.80
- 0. 000E -01 0.000E O
0.000E 209.40 0.
O.
4.40 0.000E+01 0.000E O
0.000E 270.30 0.
O.
3.60 0.000E-01 0.000E O
0.000E 323.00 0.
O.
3.20 0.000C-01 0.000E. 0 0.000E f
338.40 0.
O.
11.50 0.000E 01 0 000E O
0.000E 409.40 0.
O.
2.14 0.000C-01 0"000E 0
0.000C 463.00 0.
O.
4.00 0.000E-01, 0.000E 0
0 000C 755.20 0.
O.
1.06 0.000E-01 0.000E O
0.000E 772.10 0.
O.
1.56 0.000E-01 0.000E O
0.000E 794.80 0.
O.
4.60 0.000E-01 0.000E O
0.000E 911.07 0.
O.
27.00*
0.000E-01 0.000E O
0.000E 960.90 0.
0.
16.70 0.000E-01 0.000E O
0.000E 1587.90 0.
O.
3.60 0.000E-01 0.000E O
0.000E 1630.40 0.
O.
1.07 0.000E-01 0.000E O
0.000E U-200 HP 63 30 0.
O.
3.90*
0.000E 01 0.000E O
0.000E 93 00 64.
106.
5.60 2.738E 00 2.261E -7 7.344E -
1001.00 0.
O.
0.59 0.000E-01 0.000E O
0.000E AN-511 NP 511.01 92.
- 28. 100.00*
1.149E 00 i4.339E -8 0.091E -
\\
l l
g.
l i
60
[.
6
NUCLIDE IDENTIFICATION SYSTEM (REV 12/04)
UNKNOWN LINE REPORT PAGE 3
PK IT ENERGY AREA DKGND FWHM CHANNEL LEFT PW CTS /SEC % ERR
%Er 2
3 74.59 76.
32.
1.35 149.27 142 10 1.53E-02 21.7 2 14E 3
3 77.15 54.
64.
1.41 154.39 142 10 1.08E-02 29.5 2.24E LINES NOT MEETING
SUMMARY
CRITERIA PK NUCLIDE ENERGY HALFLIFE DECAY UCI / UNIT ABNDIFF FAILED 1 W-187 72.06 2.390E 01H 4.511E O
5.723E -7 13.34%
ABN 4 ND-147 91.10 1.106E 01D 1.145E O
5.197E -8 63.12%
ABN 4 AC-228 93.50 1.913E 00Y 1.002E O
3.625E -7 3.60%
ABN 4 U-238 93.00 9.999E 03Y 1.000E o
2.261E -7 55.51%
ABN 6 CE-143 350.61 3.300E 01H 2.978E O
1.269E -6 5.21%
ABN 7 N-13 511.00 9.970E COM 4.141E 93 1.300C 06 100.00%
DCY 7 F 18 511.00 1.097E 02M 3.533E D
1.504E 1
100.00%
DCY 7 TL-200 510.00 1.913E 00Y 1.002E O
2.013E ~7 16.90%
ABN 8 RU-103 610.33 3.935E 01D 1.039E O
7.591E -7 5.78%
ABN 8 DI-214 609.00 1.600E 03Y 1.000E O
3.606E -0 41.45%
ABN 10 DI-214 1765.00 1.600E 03Y 1.000E O
1.735E -7 61.45%
ABN g.
l
.i NUCLIDE IDENTIFICATION SYSTEM (RCV 12/34)
SUMMARY
OF NUCLIDE ACTIVITY PACC 4
TOTAL LINES IN SPCCTRUM 10 LINES NOT LISTCD IN LIBRARY 2
IDCNTIFIED IN
SUMMARY
RCPORT 4
40.00%
NATURAL PRODUCT 1-SIGMA NUCLIDC GBHR HALFLIFC DCCAY UCI / UNIT ERROR
%CRR K-40 HP 1.000E 03Y 1.000 6.922C ~7 1 140E -7 16.77 PB-214 NP 1.600C 03Y' 1.000 3.929C -0 1 239E -8 31.54 AN-511 NP 1.000C 03Y 1.000 4.339E -8 8.091C -9 18.65 em W
I
WY?Q-
-?
Nuclear Information and Resource Service 1616 P Street, N.W., Suite 160, Washington, D.C. 20036 (202) 328-0002 February 2, 1987 DIEEDOM W INFDRMATM)N Donnie Grimsley E@M
[h[f g g
Division of Rules and Records Office of Administration US Nuclear Regulatory Comrission
/
g.,
Washington, DC 20555 FREEDOM OF INFORMATION ACT REOUEST
Dear Mr. Grimsley,
Pursuant to the Freedom of Information Act, 5 U.S.C.
522, as amended, and 10 CFR 9.8 of the Commission 's regulations, the Nuclear Information and Resource Service requests the following documents pertaining to the December 3, 1986 spill from the Hatch nuclear power plant spent fuel pool.
Please consider " documents" to include reports, studies, test results, correspondence, graphs, charts, diagrams, notes and summaries of conversations and interviews, computer records, and any other forms of written communication, including internal NRC Staff memoranda.
Pursuant to this request, please provide all documents prepared or utilized by, in the possession of, or routed through the NRC related to :
1.
the precise cause of the spill, including the name and location cf any equipment which failed to work as designed, and the extent to which human error was the cause; 2.
exactly how much water spilled over what period of time from the pool and how much radiation was released. Please include a breakdown of the amount and kind of radionuclides released; 3.
the number of fuel rods in the pool at the time of the accid en t. If possible include a breakdown or timeline of when each set of rods was put in the pool starting from the first refueling outage to the present;
~
- 4. the impact of the spill on the wetlands surrounding the plant,
include any environmental assays before and/or after the accident, any follow-up currently underway or planned by the NRC or any other federal, state, or local body; 5.
the design of the fuel pool. How many others of the same or similar design are there in the United States? Does the pool have a liner? If so, what is the liner made of?;
6.
the nature and cause of any other fuel pool accident at any other US nuclear reactor and its impact on the environment.
In your response, please provide a list of offices,to which this request was forwarded.
In our opinion, it is appropriate in this case for you to waive sea'rch charges, pursuant to 5 U.S.C.
522 (a) (4) (A) "because furnishing the information can be considered as primarily benefiting the general public."
The Nuclear Information and Resource Service is a non-profit organization serving local organizations concerned about nuclear power and provides information to the general public, members of Congress, State and local officials.
If you have any questions about the nature of this request, please contact me by phone at 328-0002. We look forward to your prompt reply.
Sincerely,
.>OVQ)
LV Stephanie Murphy
.