ML19323H986
| ML19323H986 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/16/1980 |
| From: | Geckler R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19323H985 | List: |
| References | |
| NUDOCS 8006170417 | |
| Download: ML19323H986 (31) | |
Text
.
V UtilTED STATES OF A!! ERICA NUCLEAR REGULATORY COM:11SS10tl BEFORE THE AT0t11C SAFETY AflD LICENSING BOARD In the !!atter of
)
')
DAIRYLAfl0 POWER COOPERATIVE
)
Docket fio. 50-409
)
(FTOL PROCEEDING)
)
(La. Crosse Boiling Water Reactor)
)
AFFIDAVIT OF ROBERT P. GECKLER Robert P. Geckler, being duly sworn, deposes and says:
My name is Robert P. Geckler.
I am employed by the Nuclear Regulatory Commission and assigned to the Environmental Engineering Branch of the i
Division of Engineering.
At the time of the preparation of the Final I
Environnental Statement (FES) concerning the operation of the La Crosse Boiling Water Reactor (LACBUR), I was the environmental project manager for the La Crosse plant. T:le Final Environmental Statement for LACBilR was prepared under ny supervision.
The purpose of this affidavit is to respond to questions concerning the LACBilR FES submitted on flay 21, 1980 to the Applicant and Staff by the i
Atonic Safety and Licensing Board. This affidavit was prepared by me or under my supervision. fly professional qualifications are attached to this statement.
(Attachment 2) 800.61704H7
Board Question 1 With respect to Contention 2A, regarding off-gas emissions, there appear to be sone discrepancies in the radiological release figures provided in the FES.
The Staff's evaluation of releases of radio-active mterial in gaseous effluents is based on the period 1978-79, whereas the Applicant's higher estinates for noble gases,1-131 and particulates are based on actual releases during early 1977.
On the other hand, EPA estimates that releases of I-131 may be considerably higher (FES, p. A-10).
The Board desires a recon-ciliation of these estimates and, in any event, a listing of actual annual releases of gaseous effluents (particularly I-131) throughout the life of the plant.
The Board also wishes en expla-nation of why the years used by the Staff (1978-79) as a basis for estinates are more appropriate than those used by the Applicant or EPA, which apparently reflect higher release values.
Please describe in detail any mechanical or operational changes in the facility which may justify using the years chosen by the Staff.
In naking its calculation of estimated radiological releases, the Staff apparently used the parameters appearing in Table 3.6-1, including a plant capacity factor of.71.
The.71 factor was based on 9 years past operation at 0.5 and 21 years projected operation at a factor of 0.8.
In projecting for the future, why should not only the future projected factor (0.8) be used?
(In any event, is 0.8 a realistic projection?)
Response
The Staff used 1978-79 releases as a basis for their off-gas estimate since these years reflected operation with the off-gas system nodifications.
The Applicant's estimate was submitted in February of 1978 and does not reflect these nodifications. The EPA comment (FES p. A-10) does not make an estimate of releases, but points out that the Staff's radioactive estim6tes (in the DES) are high compared to the Applicant's actual reported releases, and that the Staff should factor in operational experience in their estinates. As indicated in the FES Section 3.6, paragraph 4, the Staff has used operating infomation to develop the release estimates.
t
. l To acconnodate the Board's request for annual release reports, the semi-annual effluent release reports submitted by DPC for the La Crosse plant for 1973-1979 are attached. These are the only reports available.
(Attachment 1)
The years 1978-79 are a more appropriate basis for estimating releases for the future since the plant's off-gas systen was improved in 1977.
Refer-encing FES Figure 3.6-2, the off-gas system modifications can be considered a combination of mechanical and operational changes.
The absolute filter (HEPA) and charcoal filter on the discharge of the waste gas storage tanks were not originally present and were added. The normal discharge path for the main condenser off-gas was nodified to include flow through the recoa-biner, the two waste gas storage tanks, and the new HEPA/ charcoal filter.
Previously these itens were intended to be used as an option and were normally bypassed.
Furthermore the two waste gas storage tanks were lined up to be used in series rather than parallel operation.
The overall result is longer decay time in the waste gas storage tanks and additional filtra-tion, thereby reducing the gaseous effluent releases.
The methodology used by the Staff to develop the 0.71 plant capacity factor was a means of factoring in past operating experience to provide a more
-realistic estimate.
The 0.8 plant capacity factor is an assumed plant capacity for newer plants, considered to be a 30 year average, which in the
~ Staff's opinion is capable of being attained once major maintenance problems and extended refueling outages are overcome.
Board Question 2 With respect to Contention 2B, regarding occupational exposure of workers, the FES includes a number of figures which appear to call for further explanation.
For instance, it lists 156 man-rems / year as the average LACBWR occupational exposure for the years 1970-1978 (i 5.5.2, p. 5-12).
In contrast,.it lists 600 man-rems / year / reactor unit as general past exposure experience (without defining which reactors and which years are included) (Id.). At the spent fuel pool hearing, however, the Staff testifiel that the annual worker exposures of LACBWR ranged from about 110 to 240 man-rems (Shea, direct testimony, p. 4, fol. Tr. 893).
Moreover, the Staff's Environuental Inpact Appraisal prepared in conjunction with the spent fuel pool expansion proceeding suggested that occupational exposures with the additional spent fuel might be 1% higher than earlier annual man-rem exposures (EIA, 9 8.1.2).
The Board wishes to be provided with a listing of the annual man-ren occupational exposures at LACBWR throughout its operation and an explanation for any years during which exposures were significantly above the predicted average of 156 man-rens. The Board also wishes to be provided with an analysis of man-ren l
exposures at reactors of varying sizes and an explanation as to how the _ predicted occupational exposure of 156 man-rems may be considered ALARA in view of the relatively small size of LACBUR and the relatively lower number of employees at LACBWR compared to larger reactors.
In addition, the Board wishes to be advised why average occupational exposures at Big Rock Point, Nine Mile Point, and Oyster Creek have apparently been lower than at LACBWR and whether measures used at those plants might possibly be adopted at LACBWR.
Response
The average man-ren/ year on p. 5-12 of the FES was obtained from the annual reports contained in NUREG-0594 (1979) as indicated by footnote 4 referencing this document on page 5-32.
NUREG-0594 (1979) contains a listing of the annual man-ren occupational exposures at LACBUR, As indicated by the recent correction issued concerning Chapter 5 of the FES, the 600 man-rem / year / reactor should be changed to 200 for the LACBWR F-T
plant. However, explanation of-the 600 figure is provided in FES 9 5.5.2,
- p. 5-12 wherein it is stated that:
"Therefore, past exposure experience from operating nuclear power stations has been used to provide a widely applicable estimate to be used for all light water reactor power plants of the type for La Crosse."
(i.e., all boiling water reactors).
The annual worker exposures at LACBWR reported to the Commission by DPC have ranged from a low of approximately 110(111) in 1976 to a high of approximately 240(234) in 1975 (NUREG-0594). These occupational exposures correspond with the figures cited in Mr. Shea's testimony, referenced by the Board.
The 1% increase conservatively estimated by the Staff in the EIA 6 8.1.2 concerning the spent fuel pool modification does not affect or contradict the LACBilR occupational exposures reported or predicted in the FES since the added 1% anticipated would anount to only 1-2 man-rems.
This was previously explained by the Affidavit of Dr. Donohew (p. 7), attached to the Staff's motion for summary disposition on record in the spent fuel pool proceeding.
I 1
Many factors affect the variations in annual man-rem doses from plant to plant and fron year to year.
Among these, in general order of descending f
importance, are:
(1)
Fission and Corrosion Products Fission products can enter primary coolant through leaks in fuel cladding; corrosion products can enter the primary coolant and be l) activated _by core neutrens.
Either can then be dispersed within 1
l f
1 ll il
various systens, causing elevated radiation dose rates.
These radiation levels vary substantially from plant to plant, and cannot be predicted in advance.
(2)
Special flaintenance or Equipment Replacement When equipment, piping, or components fail, and need to be repaired or replaced, workers may be exposed to very high dose rates which cannot.be estimated in advanca.
Also, it is not possible to predict how many or which components will fail in any given year.
(3) Plant Age In a typical plant, man-ren doses tend to increase over a period of several years, as the level of buildup of fission and/or corrosion products increases, and to level off.
However, actual doses, from year to year, go up or down, depending principally on (2)'above.
(4) Plant Size There is some indication that larger plants tend to experience high man-rem doses.
However, this variation does not reflect a clear, linear relationship.
Experience at large plants for example may vary in a given year from less than 100 man-rens (comparable to or less than some snaller plants) to several
-thousand man-rems.
Thus, in comparing different plants in terms of man-rems per year, it is necessary to _be aware of.a. multiplication of factors.
The principal deter-
mining factors affecting man-rea doses during a given year are the dose rates in the plant from fission and corrosion products, and the unpredict-able activities necessary to maintain, repair, and replace components or equip 1ent.
The Staff has not determined that any particular dose value would be ALARA at LACBWR.
No particular annual man-ren dose number can, of itself, be ALARA. ilhether or not radiation doses associated with any particular activity are ALARA depends upon conditions at the time, and whether reasonable actions are taken to reduce doses.
As to the Board's inquiry about exposure at the four plants listed, the Staff has no specific infonaation on hand to explain the difference in occupational exposures between the four other plants and LACBilR.
But, as explained above, the size of the plant does not deteruine the exposure rates, nor is plant size significant in this regard.
The determining factors in occupational exposures are, as previously indicated, the par-ticular naintenance requirements and operating characteristics of each plant.
For this reason, procedures in effect at other plants might not be at all relevant to the LACBWR occupational exposures.
Board Question 3 With regard to Contention 8, concerning environmental radiological monitoring, the FES suggests that the monitoring which is being j
provided is that required by Regulatory Guide 1.21 (see FES 9 6.4).
The latest revision of that Guide apparently is dated June 1974.
However, the Board is aware that the Department of Health, Educa-tion and Welfare, Public Health Service, commented critically on
the operational off-site radiological monitoring progran (FES,p.
A-4) and that the Staff declined to respond to those comments (FES, i 11.6, p. 11-8).
The Board is also aware that new and
. additional guidelines for environmental radiological monitoring have recently been developed and provided to both licensees and operating license applicants.
See Branch Technical Position (BTP), Revision 1 (November 1979) of Radiological Assessment Branch, provided to licensees by letter from W. P. Gammill, dated November 27, 1979, and to operating license applicants by letter fron Steven A. Varga, dated December 21, 1979.
(This BTP apparently updates Regulatory Guide 4.8, which was referred to in the DES but has been deleted from the FES.)
The Board wishes to be provided with a complete description of the environmental radiological monitoring program and apprised as to whether, and if so in what manner, DPC will comply with the require-ments of the foregoing BTP, Revision 1, the Board should be provided with explanations as to why particular provisions of the BTP, Revision 1, are not to be followed.
Response-Regulatory Guide 1.21:
"Heasuring, Evaluating and Reporting Radioactivity in Solid Waste in Releases of Radioactive Materials in Liquid and Gaseous Effluents Fron Light-Water-Cooled Nuclear Power Plants" is concerned with effluent nonitoring rather than radiological environmental monitoring, as explained in the FES 5 6.4, p. 6-2.
The comment on the DES by the Depart-ment of Health, Education and Welfare (FES, p. A-4) is concerned with the lack of information in the DES about the radiological environmental moni-toring done by DPC rather than a criticism of the program.
The comment of HEU in the first paragraph (FES, p. A-4) concerning off-site doses is answered in FES 5 11.5.10.
Since the radiological environnental nonitoring programs of applicants have no impact on the environment, detailed descriptions of the programs are not included in environmental statements, and for this reason, no response to the HEW comment was provided.
The Board has been provided with a complete description of the environmental radiological monitoring progran at LACBWR and a comparison with BTP 4.8, Revision 1, in Dr. Branagan's Affidavit subnitted in support of the Staff's notion for sumnary disposition served June 6, 1980.
Board Question 4 With reference to the inpacts on aquatic biota, the Board wishes to be provided with a summary listing of the LACBWR environmental studies to date, including the time that the studies were carried out and their content.
Explain the discrepancy between the range in annual commercial fish catches described in 6 2.7 of the FES (p. 2-14), and the data provided in Table 2.7-2.
Is the large decline in fish catch in Pond 9 since 1974 significant, and how does this square with statements made in the second pa-agraph of 5 10.1.2? Before construction and operation of LACBWR, were living speciments of the Higgins' pearly eye mussel found in Thief Slough or other areas nearby?
Response
The Staff does not possess a list of LACBWR environnental studies, but I have been advised that the Applicant is compiling this list for the Board.
The nunbers of comnercial fish catches contained in FES 9 2.7, p. 2-14 are in error.
The correct data is contained in Table 2.7-2.
The Wisconsin Department of Natural Resources was contacted to inquire about the decline in the Pond 9 fish catch since 1974. WDNR considers the decline to be a natural fluctuation with no definite trend as yet.
Sone of the factors influencing fishing effort (and, hence, yield) have to do with economics,droughtyears(1976,1977), and what fishes make up the catches (e.g. catfish are variable in quantity when compared with drumhead and carp,
. which are reasonably stable). Also, fishing may be better in sone areas for a period than in others, for various reasons. Thus, there is no single factor to which the reduction can be attributed and no reason is known why such a reduction in Pond 8 did not occur.
Since LACBWR takes about 2.5% of the total flow of the river during the ten year (one week) low flow, and much less on the average, it is not reasonable to attribute the fish catch reduction to the nuclear plant.
For the reasons explained, I do not believe the decline in fish catch fron Pond 9 to be significant.
FES 5 10.1.2 is an accurate statenent of the Staff's evaluation. As to the Higgins' pearly eye mussel, the Staff is not aware of any records or studies revealing the existence of this species in Thief Slough or nearby areas prior to construc-tion of LACBWR.
It should be remembered that LACBWR was constructed and began operation prior to enactment of the National Environmental Policy Act and the Endangered Species Act.
Board Question 5 In its connents on the DES, the Environmental Protection Agency indicated that, although LACBWR's cooling systen in general is in confomance with the requirements of EPA regulations, the combined discharges of LACBWR and the neighboring Genoa-3 coal-fired facil-ity result in chlorine levels exceeding those reconnended by the Wisconsin Department of Natural Resources (FES, p. A-6).
Apparen tly, LACBUR itself does not chlorinate (Id., pp. 5-20, A-7), so that
~
the entire chlorine discharge emanates from Genoa-3.
If this be so, the Board wishes to be apprised as to whether there is any action which could be taken with respect to LACBWR which could reduce the levels of chlorine emitted from the combined, connon discharge.
How could EPA's recommendation that " chlorination procedures be evaluated" be carried out? Is a proceeding in-volving an operating license for LACBUR the proper forua in which to undertake such an inquiry?
l
Response
As stated in the FES, 9 6.1.1, the Wisconsin Department of Natural Resources has issued a discharge permit for LACBWR (Pernit No. U10003239), which requires chlorine nonitoring.
Also, it is pointed out in FES 911.5 (p.
11-7) that chlorination of Genoa-3 is controlled by the Wisconsin Department of Natural Resources and is a matter outside the Commission's jurisdiction.
Board Question 6 In responding to an EPA comment concerning the use of any mate-rials containing PCBs, the Staff indicated that the Applicant had stated that materials containing PCBs are not presently used on the site and there are no plans to use any such materials in the future (FES, 9 11.5.12, p. 11-8). The Board wishes to be advised whether, if the Applicant's plans in this regard should change, the natter would be one regarded by the Applicant and/or Staff as falling within the purview of the first paragraph of the proposed license condition appearing in paragraph numbered 7 on p. ii of I
the FES.
1
Response
Since use, handling, and disposal of PCB is regulated by the Environnental Protection Agency, notice to NRC of the intent to use components containing PCB would not be required.
Board Question 7 The Applicant has recently indicated that it plans to phase out operations of LACBWR in 1990.
If various calculations in the FES I
were changed to reflect 10 more years of operation (instead of 20), what changes (if any) would result? (Among other things, j
changes in the anounts of radioactive effluents and in the need-for-power estimates might appear to be warranted, as well as i
resultant modifications to the cost-benefit balance.)
itesponse No changes in the FES would be necessary to reflect an end to operation of LACBWR in 1990. The Staff method of calculating radioactive effluents would be the sane and the results would not change to any appreciable degree.
Since the Staff projected a need for the LACBWR plant over the 1980-1990 period in FES Section 8.2.6, the need for power conclusion would not change.
Additionally, the Staff points out on p. 3-8 of the FES that a 520 title plant is proposed by DPC for the 1937-88 time period so that the FES need-for-power estimates account for a replacement of LACBWR power within ten years.
Since the FES denonstrates that the annual environmental costs of continued operation of LACBWR are minimal and that the power produced by LACBWR is a benefit to the DPC service area, the cost-benefit balance would not change and the conclusion reached in FES 910.4.2 would remain unchanged.
I have read the foregoing affidavit and swear that it is true and accurate to the best of my knowledge and belief.
y rCELJ, b'jubd.>.
Robert P. Geckler Subscribed and sworn to before me this 16th - day of June 1930 bs L L 1L l ~l Notary.fublic fly Commission Expires:
July 1.1982
7.TTACI.HENT 1 y
~~o
.4e=Jad y
oo
.c..
r@. c a.
~ u.
~ * ' ~ ~ :'., ::'.:
- o. g n..;.e..it.*,.: *.
A c L.
u.
,. o...,..
E e o. c,
~.
.,-e+-
o..,.
R,~
l o,
~.
- o. o. o. o.
~
.w
- e.
c.
<. o 888 8 8...
o o.. e.
~
.l
.e.e.
o. o.
e8-.o-l4 m
b.,.
.e o
o
.m
. e. Sem..
.~
s ce ypoO e, o D.
J K 3 4 0 3 C" o.o.
- M i
M *. **
eo.
5 4 8. t..
a.-
e nn a o.6
.e o o. o.
m c,.
e C. e o.
- o. c..* m. e. o..
o o, e.
- 8... o.88
- o. 'A ~
e n
e e
.o T.
.e.
o o o. oe.
$co e So c
c.
- r. ~ ~~
~.e.m
.o-e.
e 28 og meo e
e
~
--~~: cc-asa 4 :=
p,
. o.
c.
A.
8".8.E.. 88
- o. o. E. o e
- 3.,,= 3 c
,c
. A m,.-mnto e.
- t r.
. ~.
- o.1
-e o o a.
P e.
.o em.. P....e
@ e.
m*
.e
.m C
Cg o M.e.
4A
- o. P.
to. o..
.e s
oo gs
. o...
M. P*
.o.
. c. o.
.. 6~s~.eo.
e P. o.1
. P.
- c. en o o o.
b o.
e M.o.o.
p.
.~
e.4 m
..M o
5,
- 8... e m.
E. E.
8 o S P*
e.
- n. e...
8
~
.c.~..mC
.o P.
O s o.o.
~
888. c. ". m. e. o. " *. e..
"8 m.E...
I.g g s.9 o o. o. o.---..~.~o.,
- o.,
a s
I l
3 -~ s-ggggg 888 0
o s. d. d s. o o ~ ~.
i s. i.
ooooooooooo 3 n b.
- o. ~ o q
.M goc
.O O O b
o.
.o.
e.
a.os..
oQo i
o o.. o..
.o o
s e. s.
ooooooooooo J-
.h
.b. _e.,
~,e-
. e. ~... e..
J s =.
.e b,
~. m.
- m. C..
- e. e s.
.a, I
- o.
. ~.
e -
I
~ S c.,
.. E. g o o. C.
.m..e C".e
-e8 e
- c. m
- e.
- e.
- e. a e
c c
4.s t*
- c. o. )
.. o n. e.
-e.
4
,G
~
~
A he e.o
. e.. e.. e. e...
. e..
f.
r.
n r~
. ~. -
e,. e 5868 c.s E.
s e c. ~
w A.
. ~. c e c.
m ee-
- * - -- - ~ ~.e.
g 5:
cremmo.
o
.o
~e
- o. i o o e.
g N
6
.J..,
b
- o. n. e..
~
- e. c. c
,. e. e. c. 2 '.* ".* *
. g
. e, e.
~.
- m...; w e-O % e.
-55.
.
- a,...
e
's i.
o.
.448 c
o m.=. c a. ~ m c o
- e. e g
5
+2 v.
r m
e
....e
. e o.
oc:
J
$3 t :rI g
e og 6
3
%g
" th
(
g ti &G
& C'% ee c
J E,,
=
k
?, ?.
hy t
, b*
h
- 1. s Ie fg wg
- 2..$.
it '..: 5-p.
==,.I e
e ee 3,
t.
.a.
0
.1==
tr m.,
<n 3 i.
e 6.
e, ee B
0>
h
'4 i ~. : *r 7 t.e d
- a.'.i :
d se.
.e s *l ; ;. :. : (
.s..
- e. p eg p
- ~
- 3. q "..;: (
4 s.r y E'
- 3 g e.:..:.
.s o
- ....,;... s
-v s
t' *g i. U,
- p* C. i.,..'.s.... " s." e.. e.v. p,
. o 9--
.=.
r...e5.s c. E ** $
e I:
9 e e..
U v;....
a..
7 4..,.!m.<.
b... n
..* a 6 h.
.r y ll
.O)
A y
-.q..:.. L h.q.
- y g
.a up
.a.*
,.3 9...
- 4. e
- e. h. e... ~1.3 &
- 3l'
.y. 34 t'.
.v
- . xx.
- 4
(
. m su
...L
= d.
a.
C d.
.c f
2-
.y
- i y.-
\\f.'
5,
,M~
.y
,U a
r
'I J. 1AIRDOPNC RELf25ES l9"J4 Units
.la n.
~Feb.
Mar.
Apr.
May June 1.
Total noble'yanen-Curien 1845.56 1960.22 3443.31 4f63.24 1431.20 4351.36 2.
slotal halogenn.
Curies
'O.0017
<0.0016
~<0.0027.
<0.0025-
<0.0031
.3. ~ 1otal par ticulate qu onn
' 0.0047 radioactivity ( 8, Y )
t,
- 4 fotal tritium.
2.40 3.34 5.17 6.07 1.43.
4.79 Curien 0.90 1.25 1.53 1.65 0.90 2.17
' ~
5.
Total particulate 9~:onr. alpha radioactivity Curies
<7.0x10-*
<?.5x10-*
<5.4x10-' -<8.4x10-*
<8.2x10-'
6 Maximum noble qas'rclease rate UCi/sec
'1110 1260 2213 2309.
3088 3252
' 8.1x10-*
- 7.
Percent of applicable limit for:
a,c nobic gases -
t 6'
8 12 17 5
'16
- b. halogens
(I) 1 0.1 0.2 0.9 0.9 1.3' 1.8
- c. particulates*
, 8.
Isotope' released:
<0.2
<0.2
<0.2
<0.2
<0.2
<0.2 Curies Particulates Cs-137
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Da-La-14 0
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Sr-90 (0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Cs-134
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Sr-89
<0.0001
<0.0001
<0.0001 (0.0001
<0.0001 40.0001 Halogens 0.0004 0.0004 0.0004 0.0004 0.0004 0.0004 1-131 1-13) 0.0001 0.0002 0.0012 0.0012 0.0018
-0.0024 8
' Y I-135 0.0006 0.0004-0.0005 0.0003 0.0003
. 0.0013 Gases
<0.0010
<0.0010
<0.0010
<0.0010
<0.0010 40.0010 Xe-133m Xe-133 0
0 0
8.86 2.72 8.27
'Kr-RB 5.73 6.08 10.67 132.44 40.65-123.58 Kr-n?
97.02 102.91 180.77 351.14 107.77 327.66 Kr-nsm 142.n5 151.53 266.17 503.16 154.43 469.51 xe-130 27.35 29.01 50.96 140.36 43.08 130.98 Xe-135m 1191.19 1263.56 2219.56 1435.81 440.67 1339.78 Xc-135 282.37 299.52 526.14 910.73 279.51 849.82 Xc-137 99.05 105.07 104.56 672.91 206.52 627.90 0
0 0
503.16 154.43 469.51 Others as appropriate -(ngw3ci fy)
Reactor Power, Average NWT 146 156 155 153 39 133
- Dased on >8 day half-life particulaten.
Not on total particulates as shown in Column 3.
>[j r1 Z.
3m Z.
-g
.a
3
_7 _g o
II. 'AIE309iiC REI.IM ES l97f Units July Aug.
sept.
Oct..
Nov.
Dec.
Total 1.
Total noble gar,en Curies (887.86 6613.67 649.05' 3482.89 6062.29
'7757.98 49149 2.
Total halo <onn Curien
<0.0061
~
~
~
~
~
3.
Total particulate <tross
<0.0102
<0.0070
<0.0068
<0.0096
<0.0073
<0.0633 rarlicact ivi t y ( A,1)
R.97 7.95 0.78 4.53 7.09 11.65 64.97 4.
Total tritium Curies-2.46 2.34 1.05 0.85 1.7 1.46 18.26 5.
Total particulate gross alpha radioactivity Curles (1,15x10
<2.43x10
<l.08x10 1.12x10
<3.6x10
- 9. 4 Rx10. ~ < 1.05x10 y
6.
hxir.um nobic gas rele.tse rate pCi/sec .3235 3750 3305 3011 3675 3492 3750 7
Percent.of applicabic limit for ' t 24 22 2.2 11.7 21-26 14.24
- a. r.shic gaces
- b. halogens (883I) t 2.5 4.6 3.6 1.99 3.57 2.94 2.03
- c. particulaten*
0.52 0.53 0.53 0.25 0.24 0.24
<0.29 3
Isotcpc released:
Curies Particulates Co-137
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0012~
IM-La - 14 0
<0.0001
<0.0001
<0.0001 0.0001 0.0001 0.0001.
10.0012 Fr-90 0.0002 0.0002 0.0002
<0.0001
<0.0001
<0.0001.
50.0015-Cs-134
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 10.0012 Sr-89.
<0.0001
<0.0001
<0.0001 0.0007-0.0006 0.0007'
<0.0047 Halogens 1-131 0.0034 0.0063 0.0047 0.0027 0.0047 0.0040 0.0327 i
1-133 0.0017 0.0029 0.0013 0.0031 0.0039 0.0023 0.0186 e
1-135
<0.001
<0.001
<0.001
<0.001
<0.001
<0.001
<0.012 Ca n. "*
Xe-133m 13.09 94.58 9.28 49.81 86.69 13.19 286.49 Xc-133 195.62 264.55 26.01 139.33 242.29 377.16 1564.11 Er-aa 510.66 602.51
-59.12 317.29 552.27 540.72 3757.84 Kr-H7 743.20 705.68 69.25 371.62 646.85 617.52 4841.77 Kr-35m 207.32 214.28 21.03 112.85 196.42 282.39 1456.03 Xo-13R 2120.77 1891.51 185.61 996,10 1733.81 3411.13 18229.00 Xc-135m 1345.20 1261.23 123.76 664.19 1156.08 1225.74 8924.29 xe-135 993.92 1053.56 103.39 554.82
.965.72 987.57 6554.99 Xc-137 743.20 518.51 50.88 273.06 475.2R 77.58 3265.61 Others as appropriate (s peci f y)
Kr-89 211.79 211.79 Kr-Hs 4.65 4.65 Xc-131m 7.76-7.76 Reactor Power, Average NWT 160 137 16 90 148 162 125
- nased on >8 day half-life particulates. Not on total particulates as shown in Column 3.
H
-I>n Z
3m 2
--t n
u a
m.
m _,' w.
.m.
. w'
- w s.-
m w
.m 4
(, n
- 9 II.. AIRBORNE P.ELEASES %$
~
Units-Jan.
Feb.
Mar.
Apr.
May Junc 1.
Total. noble gases Curies 7751.02
-65R0.35 8136.96 5378.5 337.63 0
2.
Total halogons Curies 0.011 0.016 0.0133 0.011 0.0469 0.0098-3.
Total particulate gross 12.80' 7.00 0.44
<0.1 radioactivity (8,y))
11.64 -
8.57 4
Total' tritium Curies 3.3 1,62 2.67 1.16 0.77
.0.63
^
radioactivity Curies 41.52x10-'
=9.37x10**
2.09x10 ' - < 1.1x10 '
-*1.52x10 ' 'H.4x10 '
5.
Total particulate gross alpha 6.
Maximum noble gas release rate pCi/sec 5491 4906
'5658-5141 4293 0
7.
Percent of applicable limit fort 26.4 24.8 27.7 18.1 1.1 0
a, noble gases b.
halogens (lI) t 4.69 8.67 5.2 6.27 2R.77 6.5
- c. ~particulates*
'O.45 0.45 0.49 0.23 0.23 0.23 8.
Isotope released:
Curies
'0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Particulates
<0.0001
<0.0001 0.0001
<0.0001
<0.0001
<0.0001.
<0.0001 Cs-137 Ba-La-14 0
<0.0001
<0.0001
<0.0001
. <0.0001
<0.0001
<0.0001' Cs-134
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Sr-90 0.0008 0.0007 0.0008 0.0004 0.0005 0.0004 Sr-89 0.0064 0.0107 0.0071 0.0083 0.0393 0.00R6 Italogens 0.0036 0.0043 0.0052 0.0017 0.0066
<0.0002 I-131 i
y' I-133
<0.001
<0.001
<0.001
<0.001
<0.001
<0.001 I-135 17.03 15.13 18.75 34.42 2.16 0
Gases Xe-133m 273.61 232.29 287.24 316.26 19,85 0
Xe-133 539.47 457.99 566.35 460.94 20.93-0 Kr-88 604.42 581.04 718.51 557.21 34.90 0
Kr-87 246.48 209.26 258.76 20a.15 13.07 0
Kr-85m 3203.50 2719.66 3363.10 1758.77 110.41 0
Xn-138-1077.39 914.67 1131.10 772.89-4 H. 5.'
O X.:-135m 1021.5H 867.29 1072.50 n85.H4 55.61 0
Xc-135 475.14 403.3R 498.81 250.10 15.70 0
Xe-137 Others as appropriate (specify).Kr-89 205.40 174.38 215.64 112.95 7.09 0
13.45 0.84 0
Xr-85 Xe-131m 150 141 144 123 41 0
- Based on 8 day half-life particulates. Not on total particulates as shown in Column 3.
Beactor Power, Average MWT
-4>n Z
3m Z
--e
.a
.II. 1 AIRBORNE RELEASES l
Units July Aug.
Sept.
Oct.
Nov.
Dec.
Tot.el 1.
Total noble. gases Curies 0
1739.99 5010.24 7090.68 6800.#5 8299.73
-5713255 2.
Total halogens Curies
<0.003 0.0052 0.0039 0.0034 0.0036 0.0054 0.1325 3.
Total particulate gross radioactivity (6,y )
<0.1 4.01 6.52 8.52 9.53 9.97 7? 22
't.
Total tritium Curies 0.02 0.68 0.90 1.40 1.71 1.85 14.72
~,
~5.
Total particulate gross alpha radioactivity Curies
<9x10 8 1.2x10 '
2.13x10-'
2.98x10-' ~ 5.13x10-'
G.96x1C' lx10
6..
Maximum nobic gas release rate pCi/sec 0
2032 3532 3420 3451 5671 T671 7.
Percent of applicable. limit for a.
nohic gases 0
6.4 19.0 22.0 22.6 26.7 3'.3 b.
-halogeas.(888I) t
<0.15 0.22 0.38 0.93 0.94 1.R1
- 1. 3 d c.
particulates' 0.22 0.29 0.22 0.49 0.49 0.51 0.36 8.
Isotope released:
Curies Particulates
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
. <0.0001 10.001/
<0.0001 0.G906 0.0001 0.0001 0.0001 0.0002 10.0cla
~
Pa-La-140
< 0. 0 0 0 '.
<0.0001
<0.0001
<0.0001
<0.0001
< 0. 0 0 0 '.
<0.0012 Sr-90
<0.00(1
<0.000*_
<0.0001
<0,0001
. <0.0001
<0.0001 (G.0012 Cs-134 0.0007 0.0007
'O.0007 0,0018 0.0017 0.0013 0.0'10 Sr-89 Halogens
<0.001 0.0003 0.0005 0.0013 0.0013 0.0025 0.0671 1
<0.001 0.0039 0.0024 0.0011 0.0013 0.0019 0.0 M2 e
1-133
<0.001
<0.001
<0.001
<o,001
< o. 0 0 3.
<o.oci
<0.012 I-135 9
.87 11.03 51.76 r7.70 60.58 7'a.23 Cases Xo-133m 0
l'.31 32.57 255.GG J2.47
- ?7.43 7'*?.6r Xe-133 3
/1.24
? *.3. 7 C 07.74 2 0 3..'.9 0'?.*s
- .*.a.
Kr-88 0
101.09 291.C9 523.2G 3~ 2;
'6
- )'
C-Kr-R7 0
16.51 47.61 164.50 157.96
- t2.53
- *./. 6 3 Kr-85m 0
724.53 2006.26 2 /. 0 5. R 7 2310.11 2015.7G 21'"7.!7 Xe-138 0
221.G7 639.33 1 22.45 1077.78
- 313.59
;0.".5 Xo-135n 0
50.64 160,n5 f74,;;
f, $ 5
- 4 9 Sg3'.,
Xc-135
~160.$5
' a s ' '* -
0 398.58 1118.05
'191.20 ar.1.62
$ca9..[7
.xe-137 Gthers rs arr opriate (~yecity)
- r-By 0
le7.63 423.37 d54.65 233.70 523.53 7h2[77 T -ca 0
0 0
o o
)
i.
No-13;n 11.83 34.C7 223.03 219.91 269.0; 0
62 152 158 138 137
- 1. c t.
2 Reactor Power, Average MVT
- Dased on >8 day half-life particulates. Not on totri. p3-ticulates as shown in Column 3.
-4 2>
n T.
2m 2'
-4 s
o
e L
. II, ' AIRBORNE' RELEASES.1976
.I
) 6 I
OO d "
Table II -A
' Units Jan.
Feb.
Mar.
.Apr.
'May June.
. 1. -Total noble gases
- 2.
Total halogens Curies 10,205.94 6945.35 0-
.0 0-0 Curies 0.0072 0.0085 0.0031
<0.0012
<0.0014
<0.0012'
- 3.. Total particulate gross
_ _ radioactivity (8, Y) 13.28 7.65
<0.1
<0.1
<0.1'
<0.1
'4.
Total tritium Curies 3.404-
' l.694 0.042 0.081 0.001 0.150-'
5.
Total particulate gross alpha.
. radioactivity Curies 6.96x10-,
1.6x10,
<1.7x10,
<l.0x10,.
2.50x10,
9.8x10-6.
. Maximum noble gas release rate uCi/sec 3896' 5481 0
0 0
0 7.
_ Percent of applicable limit for:
- a. noble gases 1
32.9 25.3 0
0 0
0
.b.
halogens (8'8I) t 2.44 3.76 1.41 0.08
<0.07
- 0. OR -
- c. particulates*
1 0.61 0.58
<0.53
<0.02-
<0.02 (0.02 8.
Isotope released:
Curies
'Particulates Cs-137
. <0.0001
<0.0001
<0.0001'
<0.0001
<0.0001
<0.0003 Ba-La-140 0.0003 0.0002
<0.0001
<0.0001
<0.0001
<0.06S1 Sr-90
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Cs-134
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001'
< 0. 00:11 Sr-89 0.0019 0.0017 0.0019
<0.0001
<0.0001
<0.0901 Halogens-I-131 0.0033 0.0048 0.0019 0.0001
<0.0001
<0.0001 I-133 0.0029 0.0027 0.0002 0.0001
<0.0003
<0.qh01 w
I-135
<0.001
<0.001
<0.001
<0.001
<0.001
<0.001 Gases Xc-133m 74.50 15.28 0
0 0
c Xe 133 513.36 578.55 0
0 0
0 Kr-88 442.94 520.90 0
0 0
0 Kr-87 760.34 636.89 0
0 0
0 Kr-85m 236.78 243.09 0
0 0
0 Xe-138 3462.88 2053.74 0
'O O
O Xc-135m 1615.60 1209.19 0
0 0
0 Xc-135 682.78 914.70 0
0 0
0 Xe-137 1426.79 534.10 0
0 0
0 Others as appropriate (specify)
.Kr-89 650.12 232.67 0
0 0
0 Xc-131m 329.65 4.86 0
0 0
0 Xe-129m 0
0.69 0
0 0
0 Reactor Power, Average MWT 156 146 0
0 0
0
-t>
- Dased on
>8 day half-life particulates. Not on total particulates as shown Q
in Column 3.
3m 2
-4 a
A
f k
II.
AIRBORNE RELEASES 1976 Units July Aug.
Sept.
Oct.
Nov.
Dec.
. To ta l 1.
Total noble gases.
Curies 0
15806.14 24967.51 22732.61 2.
Total halogens Curies 40.0020 0.0052 0.0384 0.0074
~ 14329.24 28691.17 12367R 0.0184-0.0070 0.1010
'3.
Total particulate gross radioactivity' (8,y)
Curies
<0.1 8.86 13.49 16.83 10.76 23.83 95.20
'4.
Total tritium' Curies 0.016 1*.578 2.367 0.930 0.864 1.370 12.577 5.
Total particulate gross alpha radioactivity
. Curies
<1.2x10 #
<7.26x10-'
2.83x10-' <l.61x10-'
<9.1x10 '
9.35x10
- 3.1Rx10 '
6.
Maximum noble gas release rate pci/sec 0
16650 12808 10817 11424 13718 16650 7.
. Percent of applicable limit for:
a.
noble gases t
56.1 90.2 81.5
'51.8 103.9
-36.8 b.
halogens ('88I) 1 ~
<0.15 0.81 10.83 2.56 11.84 1.99 3.0 c.
particulates*
g
<0.53 0.54 0.60 0.49
<0.45 0.48 C.41 8.
. Isotope released:
Curies Particulates Cs-137 (0.0001
<0.0001
<0.0001
<0.0001
<C.0001
<0.0001
<0.0012 Da-La-140
<0.0001 0.0001 0.0005 0.0005 0.0001
<0.0001 so.0023 Sr-90
<0.0001
<0.0001
<0.0001
<0.0001 (0.0001
<0.0001
<0.0012 Cs-134
<0.0001
<0.0001
<0.0001
- <0.0001
<0.0001
<0.0001
<0.0012 Sr 0.0021 0.0021 0.0020 0.0017 0.0016 0.0017 0.0170 Halogens 8
?
<0.0001 0.0 Q 0.0143 0.0035 0.0157-0.0027 0.0477 I-133
<0.0009 0.0031 0.0231 0.0029 0.0017 0.0033 0.0413 I-135
<0.0010 (0.0010
<0.0010
<0.0010
<0.0010
<0.0010 Gases
. <0.012 Kr-85' O
20.55 42.44 61.38 37.26 71.73 233.36 Xe-133m 0
11.06
<i3.94 34.10 10.03 20.0R 214.09 Xe-133 0
605.3R 1183.46
'829.74 604.69 760.32
.5075.50 Kr-88 0
335.09 584.24 543.31 349.63 6%1.24 3427.40 Kr-87 0
1392.52 2321.98 2245.98 1458.72 278n.17 11596.60 Kr-85m 0
205.48 354.54 322.80 201.21 355.77 1927.67 Xe-138 0
7054.2R 10933.27 10500.19 6471.0R 14549.2" 55024.73 Xe-135m 0
2513.18 3957.35 3696.32 2401.58 3772.R9 19166.11 Xe-135 0
983.14 1657.84 1523.08 1003.05 1600.97 8365.56 Xe-137 0
2073.77 2786.37 2155.05 1295.36 3219.15 13490.59 Others.as. appropriate (specify)
Kr-89 0
575.34 796.46 609.23 398.35 R86.56 414R.7J Xe-131m 0
28.45 287.13 190.95 83.11 8.61 932.76 Xe-129m 0
0 0
0 0
0 0.69 Reactor Power, Average MWT 0
104 138 146 95 140 77
[
- Based on >8 day half-life particulates. Not on total particulates as shown in Column 3.
z 3m Z
M
_a
E
. e YY 3
1 Table II-A III.
AIRBORt3E' RELEASES ~ 1977 Units Jan.
Feb.
Mar.'
Apr.
May.
June l.~ Total noble gases Curies 28,426.54
<498.19 5128.18
,2373.62 661.305 0
-2.
Total halogens..
Curies 0.0147 0.1097 0.0322 0.0150 0.0635 0.0091'
_l3. Total particulate gross
~
radioactivity'(8,Y)
Curies.
28.46' 6.73 14.09 3.38 0.62' k0.001
.4 Total tritium'.
Curies 3.l
2,56 0.83 10.66
.0.41 0.37 5.-Total particulate gross alpha radioactivity.
Curies
<1.19x10
'a-2.93x10-'
<1.133x10-'
<1.327x10-'
-1.335x10-'<l.185x10*'
6.. Maximum noble gas release. rate uCi/see 15165 12571 13776
.1699 837 0
- 7. Percent of applicable limit for:
la.' noble t
'97.3 8.20 4.99 1.69 0.40 0
4 b.' halogens (an:I)
.5.29 75.54 1.06 1.87 32.14
-5.23
.c.
particulates*~
0.601-0.669 0.701 0.074 0.081
.0.032
. 8.' Isotope' released:
Curies Particulates Cs-137
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001
<0.0001 Da-La-140 0.0005
<0.0003 0.0003
<0.0004
<0.0004
<n.n001 Sr-90" 0.0001
'O.0001 0.0001
<0.non)
<0.0001
<0.30er Cs-134
<0.0001
<0.0001
<n.0001
<0.0001
<0.0001
<0.n001 Sr-89 0.0011 0.0010 0.0011
~0.0003 0.0003' O.0003.
Halogens Y-I-131 0.0072 0.0932 0.0014 0.0025-0.0439
<0.00M' I-133 0.0065 0.0098
<0.0022 0.0051
<0.017R
<0.0002 I-135-
<0.001
<0.0067 0.0286
<0.0074
<0.0018
<0.0021 Gases Xe-133m 25.58 13.30 19.58 17.R0 5.03 0
Kr-85 39.80 10.39 17.09 6.43 1.85 0
Xe-133 1222.34 528.21 760.58 808.98 266.44 0
Kr-88 1702.75 438.38 487.98 173.49 36.50 0
Kr-87 2461.74 512.74 466.36 98.70 14.61 0
Kr-85m 568.53 173.02 211.52 96.25 23.67 0
Xe-138 12567.37 1996.78 1087.18 68.57 3.17 0
Xe-135m 3766.52 596.79 302.08 18.44 0.53 0
Xe-135 3306.01 1205.84 1615.92 1057.71 3n5.32 0
Xo-137 2004.07 297.18 77.21 6.05 0.93 0
Others as appropriate (specify) Kr-89 699.29 112.06 57.43 8.19 1.19 0
Xo-131m 31.27 9.50 12.76 10.87 1.85 0
xe-129m 0
0 1.51
'2.28 0.40 0
Reactor Power, Average MWT 148.49 88.26 107.07 98.80 31.24 0.00 j
eBased on >B day half-life particulates. Not total particulates as shown in Line 3.
nz-
"E m
2
-4
=b-
1 4
>4 >nZ"mZ4 s E
~
-0 4
1 l
80 x
26227 R26 a
9 2
25 8~
121 1 4 521 t
74 4 4 96 n1 8 00000 G45 96505976046",9 9
o 92 27
- 8. 5 1
31 2 00000 l 00 25511 901841 ?1 4
T 4.
2O 3R 21 900 000O0 000 l569423405R64 9
4' 5-1 n7R3572n9R76 3
32315472 585076438 1
0 11111' 112 3
1 c
0 17 x
0 00000 000 0
e 00 06 30 010 00000 000 0000000000000 0
D 0
00 0
00 00000 000 0
0 00 7
00 00000 000 0
7 1
11111 116 v
0 17 x
2 00000 000 0
o 00 07 60 011 00000 000 0000000000000 0
N 0
00 3
00 00000 000 0
0 00 3
00 00000 000 0
7 1
11111 116 t
0 19 x
7 00000 000 0
c 00 01 80 010 00000 000 0000000000000 0
O 0
8
- 00 00000 000 01 00 00000 000 0
0 00 3
3 e
0 n
7 1
11111 116 i
L t
0 13 x
2 00000 000 0
p 00 03 80 012 00000 000 0000000000000 0
n e
0 00 8
00 00000 000 i
S 0
0 00 6
00 00000 000 n
wo h
B s
0 I
9 1
11111 118 s
I g
-0 11 x
8 00000 000 0
a u00 05 30 011 00000 000 0000000000000 0
e A
0 01 7
00 00000 000 s
l 0
e b
0 00 8
00 00000 000 t
a a
T l
u 0
c 5
1 11111 212 i
t Y
1 15 x'
3 00000 001 0
l 00 00 60 073~
00000 000 0000000000000 0
r u
03 4
00000 000 a
0 1 0. '
p J
0 0
00 2
00 00000 000 l
a to c
t ss ss se s
s ee ee es e
mm t
t it ii i/
311i 19 o
i rr rr ri r
932 N
n uu uu uC u
811 U CC CC Cp C
ree KXX s
e r
)
t eo y
a a
tf f
l h
a i
u p rt c
c l
i e
i a
em p
t si s
r s
s al
(
T a s
.s e
o o '
.l e e.
W p
M r
r el
.t e
g) 1g: rb a
e f
Y a
)
i g i s
e, e'
sc I
r a
l e
t6' t
ai 8
- d p
r s
a(
a' gl 8
se o
e f
S -
asl l'
p es r
v l
8 E
g n u 'y m u y e p
.ta p
A a
(
S ect uctla
- aes p
h A
e giiiii b sll eE 0 a
C l otvttvof nuet 4
r y
L bl riirino ecra'1 m
m s
e a
E oaatrat egi l7 -
4 s
3 3
m8557 a w
d R
n h p c t pc m tl oteu3a039 n 1 3 5' 3538753333 o
a aunbl rpc1L918 e333 1818881111 s P
8 C.
-~
o ll o m e o a a oi g111 s-r lll N
a a ai a aii c n h pt t s a r s r o e e r e r r r e c c e e r
R t t t d t t d x r'... s aorCDSCSlIIIsXKXKKKXXXXh o
n O
oo'Aooaae a
D TTT TTrtiPabcIP t
a t
t o
R I
G O
ca d
I e
e A
123 45 67 8
R s
a B
'I I
mory a
~
' Table II-A
[II.'AIRDORUE RELEASES $6 Units Jan.
Feb.
' Mar.
Apr.
May J m i.'
1.03x10' l.14x10' 3.47x10'
- 6. 6 i x i t'
.l.
Total Noble gases Curias-
'O O
~'
~'
~'
~'
'2.
Total halogens Curies 3.18x10 0
4.19x10 7.39x10 3.61x10 1,60x10
~'
~"
4.49x10 2.39x10 4.45x10 3.7Rx10
~'
~'
~'
~
3.
. Total particulate gross radioactivity
~5
-3.05x10
~ 5.71x10
. (3.v); with > 8 day half-lif e ~
-Curies 1.21x10 1.83x10
'5.07x10 4.83x10
~8 1~20x10
- 4. -Total tritium Curies 5.04x10 radioactivity Curies '
2.41x10
7.39x10 6.61x10 1.25x10 '
'2.82x10 2.16x10
~
.5.
Total. particulate gross' alpha
~
5.59x10
1.21x10' 7.13x10' 1.07x10
0 6.
Maximum noble gas release rate
-pCi/sec 0
7.
Percent of applicabic limit for:
. 5 '. 5 5 x 10' 3.22x10' 1.02x10'
- 1. 0 9 x 10' S.
O' 0
O 1.55x10 l.77x10'-
2.05x10
7.27x10
- a. noble gases 4.9x10
~'
~
~#
b.
I-131 3.6x10 l.07x10
'2.60x10'#
1.01x10 9.87x10
~
4.3x10-O
-c. particulates > 8 day half-life 5.7x10 '
1.51x10' l.28x10' 2.96x10 2.73x10' 3.31x10' 1
- d. Tritium 3.84x10' 4. 39 x10' 1.10x10' 2.5%x10
8.
Average Release Rates DCi/sec 0
0
~'
~'
~
6.30x10
9.04x10 1.05x10~
3.7.x10 '
- a. noble gases
~'
O b.
I-131' DCi/sec 1.18x10
~'
> 8. day half-life particulates uCi/nne 4.52x10 l.26x10
l.67x10 9.23x10
1.66x10 '
1.46xiO
~'
~'
~'
~'
- d. Tritium DCi/see 1.88x10 4.97x10 6.84x10 1.96x10 1.00x10 2.02x10 2
~'
c.
- 9.. Allowable Total Releases 1.29x10'~
1.17x10' 1.86x10' 3.53x10' 3.41x10'
- s. 04x10'
~'
~'
Cucios
~'
~'
Curien 6.43x10
5.81x10
.l.09x10 l.32x10 l.37x10 i 32x Ut
~'
- a. qases
-c.
Particulates Curios 4.50x10' 5.42x10 2.38x10' 2.87x10' 2.97x10' 2.0Hx10' d,
b.'I-131 Curies 8.R5x10 7.99x10' l.43x10' 1.71x10' 1.77x10'
'l.71x10'
- d. Tritium-Cseties 10.
Actual Releases
~'
5.47x10' 7.50x10 -
- 2. 31x 10['
a.~ Games 0
0 7.19x10' 1.28x20
- 2. 4 3x10' 1.15x 10' 0
0 3.32x10' Kr-85,
0 0
6.27x10' l.0Hx10' 4.20x10' 6.47x10' Xe-133 0
0 8.20x10' 7.15x10
2.57x10' 2.4%xio' Kr-88
'".27x10l.
Kr-87 0
0 2.35x10) 5.67x10[
2. 6 3 x 10,'
6.97x10 2.99x10 Kr-P5n H.60x10[
1.37x10' 9.76xin
0 0
4.52x10' 0
0 R.67x10' Xe-138 1.R7x10 0
0 1.95x10' 6. 0 H x 10
1.41x10'
- 1. s ix t o' Xe-135m 7. 3 7 x 10'_ '2.57x10*
2.10x10'
4. 0 5x 10" Xe-135 0
0 l.95x10 4.91x10-l.H1x10~
Xe-133m 0
0 R.17x10
~'
~'
1.15x10
s.26x10 l.3Rx10 1.69x10 '
Xc-131m 0
0 0
0 1.R4x10 1.95x10*
2.40x10' 2.22x10' Xc-129m 0
0 6.04x10' 6.94x10 8.80x10' 4.77x10*
Kr-89 Xe-137
-4
-4
.n Z'
3m 2
-4
.a 7
. L.- - -
i.
i' 4
E i
Ia.
AIPBORNE RELEASES (~on'd hk
'10.-
ActualcReleases tJnitn Jan.
Feb.
Mar. -
Ap r_._,
.fiay__.
Aunc Curten b.illalogens' LI-131' 3.lRx10 '
O 1.69x10~'
2.34x10 '
2.81x107' 9.61x1'~'
~
0
- I-133' o
4
.1.RRx10~3 2.69x10~
4.29x10~'
%.04x10~'
I-135 3
U 2.14x10~'-
2.36xlC7' 3.71x10 '
- 1. 3 t x i u ~'-
^
~
c./Particulates-1.R0x10~5 1.39x10-'
4.44x10~'
4.2Hx10~'
'Co-57:
Co-144 1.98x10 9.92x10 5 9.85x10 '
2.56x10' '1.83x10
Ce-141
. ~'
Ba+La-140 3.19x10 '
7.32x10 s 1.38x10 5.93x10-5 1.63x10-'
lCs-134 8.60x10~'-'4.95x10~'
2.14x10
'i.30x10~'
~'
~'
~'
Cs-137 7.20x10 l.09x10~5 7.79x10
- 1.05x10 5.05x10 Cr ~
.Mn-54 R.00x10~'
l.27x10 5 9.13x10~'
-5.99x10~' 'l.54x10-'
Fe-59 Co-58 4.78x10~5 8.48x10~'.
1.94x10
2.50x10-5 ~
m Co-60 3.23x10 1.34x10 9.13x10~5 9.39x10-'
2.9Rx10
'l.82x10~'
~'
.Zn-65 Zr-95.
1.47x10 '
-J.94x10 *-- 1.64x10
3.86x10
- 7.%2x10-
~'
~
Nb-95 7.10x10 5.9%x10 '
2.43x30~'. 4.31x10~'
4.66x10
1.2Hx10 '
- Cn-136 6.61x10~'
e.22x10~5 2.42x10 3.'39x10"
~ ' ~
-Cd-109 Nd-147 Cm-241 2.47x10
Sr-89 4.87x10 5 2.80x10~5 2.76x10~'
1.onx10-'
Sr-90 4.58x10
3.76x10~'
1.50x10~5
-4..
-4 en
.Z' 3m Z
, -4 a
7 Yable 1140 II. l AIRBORNC 'llELEASES ' NO Units July Aug.
Sept.
Oct.
Nov..
Dec.
Te.t i i.
11.
Total'Nobic gases Curles R.22x10 1.04x10,
1.~ 3 5x 10 ' ' 5.'76x10
'6.74x10 -
R.C6x10 - R. 4 '.x I h '-
2.
Total' halogens
. Cu r ies '-
4.00x10 '
1.11x10-1.91x10-' 6.67x10 '
l.15x10
.l.53x10" 4.; axio- '
'3.
nTotal particulate gross radioactivity
-(0,y) with > 8 day half-life 4.
'TotalItritium'
~
. Curies
.3.90x10 '
4.61x10~,I 2.87x10 ' 2.56x10
1.34x10 1.60x10-' 3li6si6I J
Curies' 1.88x10' 5.59x10-7.45x10
- 1.95x10'L
'2.03x10
.'4.11x10 '
7.6i.xiu 5.
Total'particulatejgross.aipha radioactivity?.
-Curies 4.05x10,,
5.62x10,
- 4. 77 x 10-# 6.66x10 3.7Ax10 # ;9.54x10-' 4.1Hxio-i-6.
l Maximum noble gas release rate pCi/sec 7.62x10 6.57x10 7.47x10' 4.75x10
7.51x10' 5.02x10'" " 1.' 2 i x i n ' -
L 7. : Percent of. applicable limit.for:
.a.' Noble gases.
.t 1.03x10, 1.38x10, 1.52x10' 9.40x10-'
1.52x10, R.99x10 ' l'.Nixin' *.
b.'I-131 t
2.51x10 4.42x10,.
1.08x10' 5.13x10
'9.51x10 #
'5.71x10
- i.57x i il
- 3.39x10,#
6.66x10-[
4.56x10-# 5.99x10 #
2.70x10-2.5Hx10 # %.00xin '*
c.' Particulates > 8 day half-life t
- d. Tritium t
1.06x10 3.16x10 4.36x10' 1.23x10' 1.74x10' 2.37x10'
'3.91x10' 8.
-Average Release Rates 2.25x10-5.3Rx10-'-2.34x10-'
4.15x10- ' 3.01x10'
'?. i.7 x 10 3.07xIO 5.22x10#
- a. Noble gases uci/sec 1.28x10-[.3.87x10 '
2.15x10 2.62x10 '.
7.91x10 '"7.70x10 '*
b.
I-131 OCi/sec c.
> 8 day half-life'particulates aci/see 1.46x10-1.67x10 '
1.12x10-' 9.55x10" 5.17x10 6.Inx10-'
1.oix10-'*-
d.-Tritium.
oC1/sec 7.02x10 ' 2.09x10 '
2.88x10-8 7.27x10-'
7.82x10-#'
1.57x10-' 2.40xto i*'
~
- 9.
Allowable Total Releases O ~
- a. Gases Curies 7.9Ax10',
7.50x10' H.93x10' 6,13x10' 4.46x10
R.97x10' 6.11xio' b.'I-131 Curies 1.36x10,'
1.41x10#
l.31x10 ' 1.22x10 '
l.13x10-1.34x10 ' -1.41xiq*
8
- c. Particulates Curies 1.75x10,
.1.51x10 1.50x103 4.51x10' 1.40x10' 4.55x10 - 5.27xio'
- d. Tritium Curies 1.77x10 1.77x10 1.71x10' l.58x10' 1.16x10 1.73x10' t.R0x10 #~
- 10.. Actual Releases Curies
- a. Gases Kr-85 5.88x10,'
1.R4x10-'
4.73x10 # 3.67xto'
.Xe-133 2.06x10,,
- 2. 59 x 10 ',
4.91x10#
2.22x10' 1.lix10 1.H9x10 1.7 Hx io "
Kr-88 4.56xlO, 6.17x10, 6.43x16' 3.00x10' 4.16x10' 5.14x10'
- 5. 7.'x ; o '
Kr-R7 1.13x10 2.47x10, 2.00x10' R.49x10' 3.63x10' 3.95x10
3.44x10' 4.20x10,,
5.1Rx10, 6.00x10' 2.43x10' l.97x10' 2.66x10' 1.H4xio#
Kr-R5n Xe-138 1.72x10, 3.77x10, 2.56x10' 9.24x10' 2.16x10' 6.86x10' l.0lx10' Xe-135m 4.96x10,
1.44x10, 7.14x10' 1.77x10' 3.H4x10 1.n7x10' 2.14x10 -
Xe-135 4.83x10 5.70x10 6.67x10#
Xc-133m R.05x10,
9.05x10; 2.71x10 1.87x10 3.9Ax10 1.R7xin' 1.24x10' 7.90x10' 4.95x10
7.65x10' R. '8 2x 10 '
Xe-131m 1.11x10, 2.05x10' 1.42x10' 7.81x10-6.46x10 ' 9.2Rx10' Xe-129m 2.32x10 3 1.18x10-# H.10x10 '
Kr-R9 8.20x10, 1.70x10,
- 7. 8 5x 10-'
1.41x10 '
6.70x10'
- 3. 51 x 10 '
Xe-137 3.24x10 4.23x10, 3.85x10' 9.75x10-'
2.02x10' 5.65x10' 1.19x10 ?
>g.
- Yearly Average, not total.
en Z
2m 2
-4 s-o r
y...
6 4,' -
\\
g ms 3
Tab 1'o II-D s
II,.MIRBORNE l RELEASES [ Con'd) M
_ v. -
~
Unitn "10. -- Actual Releases?
- Cursos.
'JulyJ Aug.,
. Jy t.. '
Ogjw
,,,,Jov DeG J_. ut.dU.
T m
4
- b.'Italocens.
1-131 3.42xto '
4.22x10-*
1.3Rx10 ':
6.27x10 . 1.07x10 '.-
.7'.6dx10-1 /.472x14 '
~
3.3Hx10 ' ;6.ISx10
J 4. 0Rx 10-':.1. *t4 W s 's T-133-
- 4. R 1 x 10 ..1. r.0 x 10- 5 4.43x10-'
. 6.57x10-),'5.87x10*-
- 5. 3 4 x 10-' -4. 5 2 2 x i M,
- I-135 9.90x10-1.26x10-?
-R'37x10 '
'I-132-
'I-134 1.H3x10
7.0x10-u. l. 9 0x ) *** [
g 6.11x10 '
N"Ix10-3.624xiG -
~
' c. Particulates' 5.20x10 '
- 3. 8 3 x'10-2.10x 10 '
- 6. :t 6*.n ii. '.
^
.6.60x10 '
1.04x10
- Cc-144, 3.47x10 '
2.64x10 '
.2.11x10-'
9.49x10 '*
2.66x10 *~
3.53x10 2.40s.6-'
Cc-141 1.25x10 '
'O.0xI0-1.1Ux10 #
1.60x10 ':1.80Hgi f
'Ba+La-140' l'.5Rx10 '
-2.07x10 *.
1.71x10-
1.24x10-3.3Hx10 '.
~ 7. 4 9x 3 0*' ' l. M'.x 10 '
-Cs-134
'I.45x10 '
2.51x10-?'
.3.05x10 '
2.19x10-*
2.44x10 '
R.33x10 ' 4.07x10 '
2.93x10
- 5'.797xin '
Cr-51 2.69x10 '
2.71x10
- 2. 9 8 1 x i o
- Mn-5 4 '
2.67x10-2.35x10-'
5.30x10-7 9.22x10 '
.. '2.n42xio-i-
.Fe-59 1.39x10
6.')2xi0 '
- 9. 5i x 1 o- ~*
' /,, -
.Co-58 4.88x10
1.4Rx10 '
7.57x10-'
7.36x10*'
l.H1xio '
2.95x10 t.471xit. '
'1.90x10-2.0Rx10-'
2.12x10-'
1.06x10 '
9.12x10 '
7.20x10 * / 41%xi#'
In-65' l.06x10 '
- 5. 9 4 x 10- 7 41. 6*.1x i n-
- Zr-95 6.57x10 '
1.76x10 '
3.10x 10-'. 3. 7%x 10-(
- b-9 5 -
4.51x10-'-
5.20x10-'
7.21xlo '
l.7Ax10 '
-3.15x10-'-4.170xior Pu+Ph-106 4.00x10-'-
- 4. nox i tiU
-Ru-103, 5'30x'10 '
4.90x10-'
5.1x10 *
'l.33x1'
0 2.401xiD 6.96x10 '
7.40x10-3.79 t x 14 '
.Cs-136 1.73x10 #
H.04x10
- 9.'7 7x i n-t '
Nd-147 4.17x10 '
1.R2x10-2.90x10-1.35x10 5. "2xla "
Cm-241 2.50x10-
- 9. 53x10 '
2.00x10 '
2.75x10 '
1.12x10-l.71x10 ' 6.97ax10-Sr-89' 1.57x10
- 1.4Rx10 '
5.71x10-'
6.3Rx10 ' 4.7Rxt0 '
5.45x10 ' 9.HH9xiu '
.Sr-90 9.4x10 '
1.12x10 "
4.R4x10
- 2.97x10-3.20x10 '
l.05x10 '
- 6. n 51x i ti-2.80x10 '
2.How10-
-Nb-94
-4
-4.
n 2'
. 3-m-
Z
=4 a
e e
s Table TI-A Yea
- __1979,
- 11. l AI RitOHN]; Hl:!.TMST;S Uniln Jan.
Feb.
Mar.
Apr.
May June 1.
Total suible ganen narien
- 6. 'rHx 10' 5.51x10' 8.05x10' 2.28x10' 3.76x10'
- 2. Total halolens Curien 2.41x10 '
9.16x10 '
2.90x10 '
1.67x10 '
3.70x10 '
2.07x10 '
3 rotal' particulate gross radioac-tivi ty (r,y) with < 8 day tulf-life
. Curies 1.97x10 '
1.74x10 '
l.07x10 '
9.54x10-'
1.19x10-'
2.37x10 '
4.
"'o t a l tritium Curies 4.30x10 '
2.86x10 '
1.95x10-'
4.07x10 '
4.73x10 #
2.12x10-8
.5. "'otal particulate <Jrosn alpha radioactivity Curies 1.30x10 '
1.54x10 ' '8.54x10 '
3.73x10 '
1.25x10-'
5.59x10 *
- 6. flaximum noble gan re l e.ine rate pCi/rn-4HU 3867 3714 237H 5672
- 7.. Percent of~ applicable limit, for:
a.
nobic ganen 1
1.00 13.10 1.22 0.85 -
0.73 1.,
1-131 1
1.62x10 '
4.40x10 '
1.77x10 '
7.63x10 #
3.6Bx10-#
8.43x10 '
particulates <H day ha1f-1 ire 1
4.05x10 #
4.17x10 #
9.87x10 '
1.50x10-'
2.41x10 '
- 5. 41x10 '
c.
d.
Tritium 1
2.86x10-1.74x10 '
1.07x10 '
2.32x10 '
2.61x10 '
l.20x10-*
- 8. Average Release It.e tes a.
noble gases pCi/sce 260.62 2.28x10' 300.41 85.05 145.09 n
b.
I-131 pCi/sec 6. 72x10 '
2.24x10 '
9.02x10 '
3.89x10 '
1.87x10 '
4.30x10 '
<8 day half
'.ife particulates pCi/sec 7. 04 x 10 '
7.31x10 '
4.67x10 '
3.09x10 5 4.66x10 '
9.89x10 '
c.
d.
Tritium pCi/sm 1. 61x10 '
1.18x10 '
7.29x10 '
1.57x10 '
1.77x10 #
8.19x10 '
- 9. Allowable Total Releanes a.
ganen Otrien 6.46x10'
'4.22x10' 6.62x10' 2.72x10' 2.67x10' 5.13x10' I.
1-131 01 ries 1.16x10 '
1.22x10 '
1.17x10 '
1.58x10 '
1.30x10 '
1.22x10 '
c.
particulates 0 ries 1.36x10
- 1. 3 7x 10' 1.36x10' 2.05x10' 1.62x10'
- 1. 50x 10'
- d. Tri t. ium s
Claries 1.50x10 1.65x10' 1.82x10' 1.76x10' 1.82x10' 1.76x10'
- 10. Ac t.ua l Re lcaners a.
(;anen Kr-HS Curies 1.77x10,'
3.93x10(
1.13x10[
Kr-n5m Kr-87 Curies 1. 57x10,
6.57x10, 1,66x10, 3.24x10 7.35x10, Curlen 5.81x10, 0.57x10, 1.89x10, 3.20x10, 2.52x10, Kr-R8 Kr-89 Curien 3.90x10 4.49x10 2.70x10 1.11x10 1.63x10, Curies Xe-129m 1.93x10,
-4 Xe-13im Curies 4. 4 3x10-2.3nx10,
3.01x10,
6.02x10-curren 2.23xlu,
1.04x10, 5.23x10~,
6.67x10,
2.44x107, Xe-13 'm Xc-113 Curien 2. 58:c10, 6.07x10, 4.33x10, 6.65x10,
1.39x10, 2
x-Xe-135 Curlen 7. 4 6x10, 1.12x10, 2.84x10, Xe-135m Curies 1. 82x10, 6.35x10, 3.89x10 9.22x107 1.55x10, Q
2.40x10, 1.39x10, Xc-137 Curies 6. 42x10, 7.52x10 5.45x10, 2.80x10, 1.93x10,
-1 Xc-130 Curies 2.12x10, 3
1.53x10, 1.12x10, 1.14x10
~^
Curies 2.40x10 2.63x]O 1.80x10 1.17x10 7.81x10,
c 3 -
- " 1; a
'll.
AiltHORNI;. RIII I'.AS CS (INJ. 2).
Table II-D Year 1979 10 Ac t;ua l fieleanen thij t_n Ja ri.
I'c h.
Mar.
Apr.
May June it.
II.i l oise n s 1-131 Curies 1.88x10-5.35x10, 2.07x10, 'I.20x10-4.79x10~,
1.03x10,,
1-132 Curies
. 4.90x10-1.89x10, 5.33x10, 4.32x10,
1.84x10-
- 8. 6 5 x 10~,,
9.47x10~,
5.73x10 g 1.20x10',
9.82x10,
T-131 Curien 1-134 Curies 2.57x10, 1.23x10 g 4.37x10,.
1-135 Curies 3.22x10,
1.92x10-1.67x10-2.72x10, - 1.26x10-1.65x10.
c.
l'a r t_ i cu la tes Cr-51 rurien 5.72x10, 3.24x10, 4.23x10, 4.76x10,
1.11x10,
8.51x10,
Mn-54 Curies
- 2. %x10- -
2.12x10,
2.95x10,
2.77x10,
l'e-59 Cuiicn 1.13x10,
- 1. 5 0x l ? ",
7.96x10,
8.70x10~,
Co-57 Curies 1.73x10,,
3.37x10-2.62x10,
- 3. 68 x ! ')-
3.71x10,
1.80x10~,
9.02x10-9.25x10~,
7.10x10',
7.70x10,
Co-511 ruries 4.56x10,
co-60 Curies 1.06x10,
6.49x10-8.89x10,,
2.09x10,
1.72x10,
3.77x10~,
Zu-65 Curies 3.59x10-3.67x10-1.03x10~
1.86x10,
8.43x10,,
Se-75 Curies 2.36x10,,
1.70x10,
- 2. 0 7x 10 ~,,
Sr-89 Curies 1.12x10,, 9.37x10~
6.10x10 3 9.11x10,
1.86x10,
2.44x103 I(
1 Sr-90 Curien
- 1. 5 Hx 10~,,
2.10x10~,,
3.10x10,
1.05x10~,
1.82x10,
5.36x10-Zr-95 Curies 1.01x10-8.56x10~,
2.49x10-1.48x10,
2.16x10,
rab-9 4 Curies 4.30x10,
6.40x10,
1.17x10,
1.02x10,
rib-95 Curies 1.83x10, 2.90x10, 1.34x10,
2.97x10',
4.35x10,
3.01x10,
Itu-10 3 Curies 7.00x10, 9.41x10, 3.79x10, 1.69x10,
1.15 x10 ~,,
1.00x10~
Itu t ith-106 Curies 2.45x10-3.13x10~,
1.99x10-2.36x10,
1.84x10,
2.10x10,3-Cd-109 Curies 3.63x10, 1.34x10-1.40x10, 1.46x10,
1.64x10,
2.03x10,
Sb-125 Curies 1.36x10,
1.33x10,
5.26x10,,
Cs-134 Curies 6.55x10-3.06x10~,
1.76x10',
1.99x10-3.44x10-1.42x10-Cs-136 Curien 7.03x10,
Cn-137 Curies 5.04x10, 5.79x10-1.31x10,
- 3. 4 7 x 10',,
4.40x10,
1.11x10,,
na-131 curi<n 1.39x10 3 2.67x10, 6.27x10,,
1.64x10,
1.58x103 Itci e l i-14 0 Curien 3.H6x10, 3.51x10, 2.09x10, 9.94x10,
7.18x10,
4.08x10-Cc-141 Curien 4.82x10,, 2.90x10, 1.69x10,
1.77x10,
1.30x10,
2.74x10,,
Ce-144 Curien 1.fl7x10~
1.77x10, 2.58x10, 2.94x10,
1.26x10,
6.S6x10,
Nd-147.
Curies 9.88x10, 1.26x10, 1.23x10, 1.95x10,
2.09x10,
2.98x10,
Cm-241 Curies 8.00x10' 8.41x10-2.62x10-5.37x10-1.03x10-3.55x10-
. ]>
- n a
3 rTi 2"
-4 1
a i-e
u v
o e
e TAtel.I: II-C Year 1979 1I, AlItttOftNE ItEI.EhSES Units
.lis l y Aug.
Sept.
Oct.
Nov.
Dec.
Tota 1 1.
Ti t ta l noble ganen narie.
4.00x10' 2.69x10' 3.00x10 4.66x10' 6.29x10' 6.84x10 1.037x10'
?.
To t.i l h.i l ogen n 0 rien
- 7. 71x 10
4.62x10 ' 1.80x10 ' 2.40x10 ' l.44x10 ' 8.79x10 ' 2.210x10-I.
T.it.n l gi.o r t i cu la t e. st ronn r.iet iesact ivi I v (1,
y) weIh il elay lia I l'- I i I e
' Oirion 1.H7xI0 ' 4.39x10 ' 3.35x10 4.42x10 ' 3.24x10 ' 3.18x10 ' 3.174x10-4 T..t.i l t r i t ium Gir ier.
4.72x10 ' 8.11x10 ' 4.12x10 ' 3.06x10 ' 5.88x10 ' 8.43x10-4.596xto'
's.
Tot.it particulate grons alpha r.u t i o-act ivity Oiries 3.73x10 ' 2.68x10 ' 4.08x10 1.20x10 ' 1.01x10 ' 2.05x10 ' 2.093x10 '
6 Maximum nol>1e gan relcase rate
- Ci/r(c 54 f14 3236 3167 4168 5050 5009 v72 7.
Percent of aI> plication limit for:
a.
nol)le gasen 1L 0.67 0.42 0.56 0.90 1.24 1.10 1.823 1.40x10' 1.48x10
2.73x10-[3.16x10-[':3.86x10-['4.71x10.'4.17x10-[.1.59x10 le.
T-131
?.
c.
particulates > 8 day ha lf-life
?.
2.97x10-2.51x10-1.65x10-4.890x10 al.
t ri t i tim 9.
2.59x10" 4.45x10-2.34x10-1.68x10-3.34x10-4.63x10-2.199x10-8.
Average Itclease Ita t en nolil e qanen DCi/r.ec 149.46 100.31,
115.74,,
173.81 242.7 255.4 171.38 le.
1-1 11 pCi/ sis; I.H2x10,, 4.71x10~, 4. 6 8 x 10 ~,,
- 5. 6 9x 10,
2.13x10, 1.26x10-3.629x10,
c.
>8 < lay half-life particulates DCi/sec 1.57x10, 1.51x10
1.41x10-1.86x10-1.05x10-1.30x10, 1.031x10,
cl.
tritium pCi/sec 1.76x10-3.03x10, 1.59x10, 1.14x10, 1.91x10, 3.15x10, 1.438x10-9.
Allowable Tot 11 lielea ses a.
qases Curies 5.93x10, 6.42x10, 5.36x10,, 5.16x10, 4.85x10J 2.97x10], 6.198x10,,.
I 5.09x10, 6.20x10 b.
1-131 Curies 3.02x10-4.35x10; 2.88x10-2.87x10-2.904x10, c.
particulates Curies 1.98x10, 5.75x10, 3.74x10, 3.79x10 2.58x10 3.65x10, 3.275x10 3
s 3
1.
tritium Q ries 1.82x10 1.82x10 1.76x10 1.82x10 1.76x10 1.82x10 2.111x10 10.
Act tia l iteleanen a.
q inen K r - B r, onrien 1.16x10-'
4.58x10-'
2.92x10' 2.00x10" 9.714x10' Kr-85m 02rics 9.03x10' 6.88x10' 8.24x10' 1.38x10' 1.86x10' 1.90x10' 1.841x10' Kr-87 Qirien 3.56x10' 5.86x10' 1.11x10' 2.21x10' 2.80x10' 2.77x10' 1.121x10' Kr-88 O' ries 1.83x10' 1.52x10' 1.30x10' 2.46x10' 3.25x10' 3.36x10' 6.804xld' Kr-89 010i08 8.63x10' 5.78x10-8 3.48x10-'
1.74x10' 1.323x10 xe-120m cirien 1.56x10-2 4.86x10 3.86x10-' 9.28x10 8.57x10 4.63x10# 7.002x10 J
Xc-111m 08EIC3 7.51x10~'
1.38x10' 1.74x10' 2.06x10' 8.56x10-'
5.62x10' 9.446x1" Xc-133m 01riCS 3.50x10'
- 3. 8 5 x10' 4.22x10' 4.52x10' 4.55x10' 6.54x10' 8.059x1 Xe-113 omries 1, 4 4 x 1 pt
- 2. 2 3x 10' 2.61x10' 5.00x10' 5.34x10' 6.96x10' Xc-I]5 Giries 2.06x10'
- 2. 04 x 10' 2.17x10' 3.24x10 4.49x10' 4.81x10'
- 7. 228x1 ' >
2 3.250x10 l
xc-1 15n, Girien 4.75x10e 1.62x10'
- 3. 29x10' 4.26x10' 8.09x10' 9.70x10' 9.007x10' xe-I 17 Oirien
- 2. 02x 10' l. 4 8 x 10' 2.29x10" 2.10x10' 4.12x10' 4.90x10' O.040x10'j>
Xe-138 Girien 7.71x108 5.23x10' 1.17x10' 1.44x10' 2.82x10' 3.01x10' 3.250x10,c5 x
3m Z
-4
-.s
a e
i e
i e
a a
e i
I i
I 8
I 8
I a
e s
.a i
s; e.
a TADLE II-D Year 1979 11.
A I RBORill lil:I,I ASICS tinitn July Aug.
Sept.
Oct.
Nov.
Dec.
Total 10.
Act u.e l Heleason (Cout.)
h-h.iloieun 15-131 Curies 4.48x10-' l.37x10-'
1.11x10-' 1.35x10-' 7.19x10-' 3.10x10-' l.38x10 '
l-132 Curies 2.86x10 ' 1.23x10 ' 5.11x10 ' 5.70x10-' 1.08x10-' 7.49x10-8 1.83x10 '
i-131 Curies 2.44x10-' 2.05x10-'
4.51x10 ' 9.12x10 ' 4.25x10-' 1.38x10 ' 7.63x10-8 1-134 Curies 2.98x10 ' 5.85x10 5 8.57x10 5 3.40x10 ' 8.01x10 '
l-135 Curies 4.77x10 ' 1.Olx10 '
2.29x10-' 4.49x10-' 1.85x10 ' 8.30x10-' 2.36x10-'
c.
particulaten Cr-51 Curien 1.64x10,, 1.18x10,
8.65x10, 6.58x10, 1.81x10, 1.43x10_, 1.73x10,
s s.
rin 'd curien 2.59x10, 2.43x10,
7.79x10, 3.01x10~, 1.48x10-4.23x10, 2.03x10 3 l'e-5 9 _
Curien 1.77x10, 9.83x10, 2.44x10, 8.60x10, 2.65x10, 2.74x10~, 1.58x10-co-57 Curien-5.51x10, 3.48x10, 8.25x10, 1.45x10-1.56x10, 4.13x10~, 8.46x10,
Co-su Curies 5.17x10, 4.20x10 3 7.35x10, 4.66x10,, 1.79x10~, 2.69x10-7.15x10,
co-60 Curies 3.37x10, 4.16x10,
2.44x10, 3.17x10, 3.71x10 3 3.78x10, 3.08x10 3 zn-65 Curies 2.53x10, 4.98x10-4.00x10, 8.66x10 3 1.66x10-4.28x10 3 So-75 Curics 1.93x10~,
7.31x10, 1.98x10~,
, 1.07x10, 4.59x10,
Sr-89 Curies 9.20x10-1.70x10,
1.08x10-2.29x10, 5.15x10, 3.77x10, 5.57x10,
Sr-90 Curies 1.36x10-8.78x10-3.07x10-7.34x10-1.24x10-Y-91 Curies
- 1. 0 6x10~,' 1.06x10
- Zr-95 Curies 3.00x10~, 3.22x10, 1.32x10, 1.73x10-8.63x10-1.02x10, 2.69x10,
Hb 94 Curies 1.27x10~. 1.03x10, 1.50x10,
7.20x10, 7.20x10 3 9
Nh - )5 Curies 1.56x10, 3.25x10,
1.46x10, 1.20x10, 3.22x10~, 1.59x10,.2.49x10,
Hu 103 Curies 5.97x10 3 -5.61x10 3 4.78x10, 3.0lx10, 3.20x10 3 1.91x10, 2.47x10,
HutRh-106 Curies 3.15x10, 5.25x10 3 9.33x10, 8.98x10, 1.55x10, 1.78x10-2.49x10,
Cd-101 Curien 4.39x10-7.81x10,
1.57x10-2.83x10~, 5.09x10-1.33x10, 3.13x10,
St-12?
Curies 2.05x10, 2.12x10, 2.37x10,
2.79x10~,
Sh-125 Curies 1.02x10,
1.51x10, 2.40x10, 8.30x10-1.37x10,
Cn-134 Curica
, 5.32x10, 3.35x10, 1.14x10~, 3.20x10, 1.12x10, 2.05x10 3 Cs-136 Curies 4.68x10 3 1.60x10 3 1.44x10, 1.66x10~, 3.68x10~
3 1.04x10",
Gn-137 Curien 1.26x10, 1.06x10, 1.28x10, 1.22x10, 1.15x10, 1.33x10~, 1.16x10,
na - 1 13 Curies 1.34x10, 2.22x10, 5.13x10, 4.86x10, 7.89x10, 2.64x10, 1.64x10,
lu t i.a-14 0 Curies 1.11x10-1.47x10-1.05x10-8.88x10-6.38x10-1.21x10, 7.89x10,
cc-139 Curies
, 2.14x10, 2.14x10 3 Cc-141 Curien 1.60x10, 2.48x10,
1.70x10, 1.75x10, 1.48x10~, 8.02x10 3 1.81x10 3 Cc-144 Curien 7.00x10, 1.86x10,
6.87x10 g 8.77x10, 6.88x10-1.74x10, 9.41x10 3 Nd-147 Curies 3.15x10-8.79x10-1.76x10-4.06x10-2.65x10, 1.27x10~, 3.22x10,
H Am-241 Curles
, 2.41x10, 2.41x10-D' Cm-241 Curies 4.18x10-3.98x10-1.60x10, 1.75x10', 2.44x10-cm-243 Curies 2.62x10, 2.84x10,,
5.62x10-5.62x10-2rn 2-s a
~
12/79 ATTACHMENT 2 PROFESSIONAL QUALIFICATIONS ROBERT P. GECKLER U. S. NUCLEAR REGULATORY COMMISSION I am a Senior Environmental Project Manager for the U. S. Nuclear Reg-ulatory Ccamission(NRC), having joined the staff in 1972. As an Environmental Project Manager (EPM) I am responsible for the management of the review of an applicant's environmental reports and the preparation of NRC Environmental Statements which meet the requirements of 10 CFR, part 51 and the National Environmental Policy Act of 1969 in connection with applications for construc-tion. permits, _ operating licenses and amendments for nuclear power plants.
I also act as the main point of contact between the NRC and the cpplicant in matters' relating to environmental affairs.
I _have held assignments in various capacities as the EPM on the LACBNR, Bailly Nuclear Station, Calvert Cliffs, Hatch, Indian Point, Seabrook Nuclear Station, Farley, South Dade, Brunswick, Pebble Springs and Palisades.
In ad-
)
dition, I have held a number of special assignments, including such areas as generic prcblems of alternative siting, cost-benefit analysis, monitoring re-quirements, workshops on biological significance and committee membership on a ecmmittee between EPA and the NRC, evaluation of research proposals and re-View of internal staff documents.
Prior to joining the NRC, I spent approximately five years as a Senior Research Ass aiate in the Biomathematics Program, Statistics Department, at North Carolina State University, Raleigh, N. C.
As a faculty member and as-sociate member. of the graduate faculty, I taught courses in resource manage-
. ment and biology at the advanced undergraduate and graduate level, assisted in organizing and giving a course in systems ecology, participated in graduate
(
student guidance, program administration and research in prey-predation in an aquatic system (snails and marsh flies).
I was also a member of the Nutrition Institute and the Air Pollution faculty.
Outside consulting activities in-cluded general toxicology and toxicology of atmospheric pollutants.
Before joining NCSU, I was employed by Aerojet-General C'orporation in California and Ohio for eleven years, three of which were with the company's nuclear division. While with the nuclear division, I had several assign-ments including those of Project Engineer for manufacture and assembly, i
including critical assembly, of nuclear training reactors and Administra-tive Reactor Supervisor. I held an AEC Reactor Operator License for Aero-jet-General reactors.
..In11960, I transferred within the company to assist in establishing a life sciences activity.
I participated in all phases of life sciences pro-grams'and_was responsible for the biological research withid the Corporation.
Y o
g O.
ATTACHMENT 2 Robert P. Geckler O Programs included establishing and operating an inhalation toxicology labora-tory at Wright-Patterson Air Force Base, Ohio.
I was Project Engineer during the early phases of design and fabrication and later Assistant Laboratory Direc-tor.
Other programs included systems studies of waste management processes, the relationships between solid wastes and disease, needs in solid waste research, water purification and microbial problens in desalination, river purification, recreational water criteria, various problems associated with manned space flight and. life support systems (including the manned Mars Mission), research and development leading to the fabrication of a photosynthetic gas exchanger and study of man in confinement. Special assignments were accepted as a life science specialist within the corporation. My final position with the company was Assistant Manager, Life Sciences Division and Manager of the Advanced Bio-logical Applications Department.
Before my employment with Aerojet, I spent one year in military operations research and more-than four years with the AEC, Oak Ridge Operations Office, Isotopes Division and Division of Research and Medicine as a Physiologist and Biologist.
From 1949-51, I was a faculty member in the Biology Department at Vander-bilt University, Nashville, Tennessee, where I taught general biology, genetics, ytology and did research in protozoan genetics.
I received my B. S. in Chemistry and Ph D.in zoology from Indiana University in 1944 and 1949, respectively. I was granted an M. S. in Biological Chemistry from the University of Michigan in 1946.
I a m. responsible for approximately a dozen environmental statements for the NRC.
In addition, I am author of co-author of more than thirty unclassified scientific papers, and co-holder of a patent on the use of concentrated carbon dioxide for growing algae and have been listed inAmerican Men of Science since 1954.
I am or have been a member of Sigma Xi, Phi Lambda Upsilon, the American Society of Naturalists, the American Society of Zoologists and numerous other scientific societies.
I held a NIH predoctoral fellowship for two years (1947-49),
l
__