ML20063P808

Second Supplemental Response to First Set of Interrogatories.Certificate of Svc Encl.Related Correspondence

ML20063P808
Person / Time
Site:	Armed Forces Radiobiology Research Institute
Issue date:	10/08/1982
From:	Macklin L CITIZENS FOR NUCLEAR REACTOR SAFETY, INC., INSTITUTE FOR PUBLIC REPRESENTATION
To:
References
NUDOCS 8210150317
Download: ML20063P808 (49)

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RELATED CORRESPONDENCR

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION $ @ N g.@ ,

In the Matter of ) 0FFIC{0F 5gSECRil.g:

) Docket No. 50b0 B CH ARMED FORCES RADIOBIOLOGY )

RESEARCH INSTITUTE ) (Applicat. ion to Renew

) Facility License (TRIGA-Type Reactor) ) No. R-84)

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INTERVENOR CNRS' SECOND SUPPLEMENTAL RESPONSE TO LICENSEE'S FIRST SET OF INTERROGATORIES Now comes the Intervenor in the above-captioned case and pursuant to 10 C.F.R. 52.740b and the Board's Order dated July 12, 1982, further supplements its response to the Licensee's first set of interrogatories as follows.

INTERROGATORY ? '

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Answered by Dr. Stillman.

7b. The basis for the inference that the Licensee only considers the effects of inadvertent transients that result in low temperature (e.g., 100*C or less), is their own assumption that such a transient would always produce maximum gap activities of less than 1.5 percent and, specifically, a maximum release of radiciodines of only 0.2 percent. If one refers to General Atomic Company -

reports (e.g., Report No. 4314, Feb. 1980) on the properties of TRIGA fuel elements, the data graphically represents that such small radioactive gap activities must correspond to relatively low fuel temperatures (i.e., 100*C or less).

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It is especially noteworthy, on the other hand, that the

. Safety Evaluation Report prepared by the Office of Nuclear Reactor Regulation (of the NRC) reports (on page 4-7, entitled Excess Reactivity) that "the General Atomic work has indicated that a measured fuel temperature of 600*C in the B or C ring as a result of a pulse implies that local transient peaks in fuel temperature may approach 950*C."

7c. Pages 4-7 of the SER (prepared by the Office of Nuclear Reactor Regulation) clearly state that during a power transient that produces a significant tiemperature elevation "this temperature peakling is in the periphery of the fuel element; it decreases within seconds after the pulse is complete as the zicronium-hydride alloy redis-tributes the heat by thermal conduction." Thus, for a few seconds the " cladding temperature will essentially mirror the fuel temperature during a pulse operation or inadvertent transient as postulated in our original answers.

7d. The elevated fuel temperature is specifically supposed to reach any temperature in excess of 900*C. .

As indicated above (answer 7b) the SER acknowledges that

" local transient peaks in fuel temperature may approach 950*C." In many experiments with TRIGA fuel elements performed by the. General Atomic Company, fuel temperature elevations in exedss of 1,000*C are routinely achieved.'

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1. 4 7e.l. The reactivity insertion to have occurred is rapid reactivity insertion greater than or equal to 3.5 percent /1V/V (5.00) . Note that the maximum reactivity transient of 3.5 percent 26 v/V necessarily assumes that " loading is limited by the Technical Specifications" and the absence of instrumental accidents or human error (e.g., miscalculation of experimental reactivity). It is precisely when human error or mechanical mishap occurs that you are apt to violate the Technical Specifications resulting in atlarge, inadvertent power transient.

7e.2. The maximum power level this " inadvertent transient" is supposed to reach is between 2,000 and 10,000 MW.

7e.4. Any set of accidential circumstances which significantly affects the physical integrity of the fuel element itself or the moderating activity of the tank water, may interfere with the " prompt, negative temperature coefficient of reactivity of the fuel-moderator which ordinarily controls a planned (i.e. , non-accidental) transient. The exact mechanisms by which such a failure could occur are discussed in detail elsewhere in our answers to these interrogatories. ,

7j. The mechanism suggested by the Intervenor was that repeated use of the pulse mbde could produce pulse heating with temperatures in excess of 600*C. At

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There is a General Atomic Company report devoted to the effects of " pulse heating" on the TRIGA fuel-moderator and several GAC reports on the release of radioactive gases into the gap as a function of temperature, both should be readily available to the Licensee.

7n. A cladding failure is more apt to occur at fuel temperatures.above 1,000*C (see the effects of sharp temperature fluctuations on the integrity of fuel element claddings'in H.H. Hausner and J.F. Schumar in " Nuclear Fuel Elements") and total gap pressures in excess of 1,800 psi (see Safety Reports on AFRRI contained in Docket No. 50-170).

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INTERROGATORY 9 Answered by Dr. Stillman.

9a. The Intervenors wish to make clear that we are concerned only with multiple rack failures and not with single storage rack failure. If no provision is made to remove spent fuel elements from the reactor pool, it will not take.very long before there are several racks of highly activated fuel elements. The calculations by which AFRRI claims that contact among 65 spent elements ,

on the bottom of the reactor pool could become critical have not been publicly presented; we merely would like to analyze these calculations and their underlying assumptions.

That contact anong spent fuel elements may be dangerous is common scientific knowledge and needs little documenta-tion regarding its " great severity" should such an accident occur. Our'overiding concern is exactly what steps are now being taken by the Licensee to prevent such accidents.

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INTERROGATORY 10 Answered by Dr. Stillman.

10h. Both Exposure Room #2 and the In-Core Experiment Tube provide exposure facilities that are subject to high thermal neutron flux densities. They are used primarily for the production of radioisotopes and the activation of specimens and samples. The absence of a dd-Gd shield for ER #2 also results in a greater rate of Arcon-41 pro-duction. Depending on the specific experiment in progress at the time of experiment failure, one could obtain dangerous concentrations of relatively long-lived radioisotopes (both gaseous and condensed). Some potentially dangerous radio-active gases are:

Ar-41 N-13 ,

0-15 in excess of 1 Ci I-125 Xe-133 j whereas condensed radionuclides might include Cr-51\

Co-60 Co-58 ) in excess of 1 mci K-40 ,

Mn-56 l Zn-65 .

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INTERROGATORIES 12 to 22 Answered by Dr. Stillman.

These questions all refer to specific malfunctions and violations incurred by the AFRRI during their operation of the TRIGA reactor. It makes no sense for us, as outsiders, to second guess information which is more readily available to them through their own documents or by their direct observation and measurement. The charges we have made are a matter of public record and are in full agreement with the designated regulations and technical specifications n'ecessary to operate the TRIGA reactor safely. If the Licensee is serio.us about trying to remedy these situa-tions by including our technical input, we recommend that they consult with us or the Union of Concern Scientists on some formal basis-. Let there be absolutely no doubt that we consider these documented malfunctions and violations as strong indications of serious potential, repeatable dangers to the public should AFRRI continue to operate their TRIGA reactor. If such malfunctions or violations were harmless, we doubt that they would be so carefully ,

scrutinized by the NRC who, among other things, requires that they be reported immediately. We further suspect that any inclination to " dissociate" oneself from such mishaps must surely rest with the Licensee and not the Intervenors, as charged.

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INTERROGATORY 26 Answered by Dr. Ernest Sternglass and Elizabeth Entwisle.

269 Any corrective actions AFRRI may have undertaken l are inadequate as long as the serious deficiencies cited in CN RS ' Response to Interrogatory 27a, infra, in the moni toring of the air, the coil, the vegetation and the animals within a few miles of the facility are permitted to continue.

1 261. As indicated in response to 26(g) above, the )

l serious deficiencies in equipment and monitoring methods l would have to be corrected for any nuclear reactor facility, especially for one that requires the routine discharges of i i

radioactive gases at the rate'of 20 curies per year, in l excess of that measured for some large PWR reactors during the early years of operation.

However, in the present situation, where serious biological effects may have been produced in the nearby population due to the inadequacy of the monitoring system employed, the petitioners could not be satisfied that the facility can be operated safely in the future without -

a detailed, independently conducted epidemiological study of possible effects on human. health in the area surrounding l

the AFRRI-TRIGA facility. The Intervenor takes the I -

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position that such a study is necessary because the human body, in particular that of the developing fetus, infant and young child, sick and aged person, is exquisitely-more sensitive to the presence of radiation than any monitoring equipment or method yet devised by man. Since the human body is by definition the best environmental monitoring " device" for detecting biologically significant quantities of radiation, an independent epidemiological study is the only procedure that would satisfy the Intervenor that proper monitoring methods are or are not in use at AFRRI for checking emissions from routine operations.

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INTERROGATORY 27 Answered by Dr. Ernest Sternglass and Elizabeth Entwisle.

27a.l. The use of film to detect external gamma radiation is a technique that is much inferior to the use of thermoluminescent dosimeters, whose sensitivity is much greater and far more *: reliable. ,

2. No provision exists for obtaining a series of air-samples from a ring of such filters located around the facility. It has been well established in the literature that continuous air-sampling can detect a quantity of radio-active materials smaller than film. badges by a factor of about 5000 times. (The article by C.A. Pelletier " Performance and Design of an Environmental Survey," in " Environmental Surveillance in the Vicinity of Nuclear Facilities,"

edited by W.C. Reining, C.C. Thomas Publishing Company (1970).) Since the plume can frequently pass between such I air-samplers as pointed out by Pelletier, a series of such devices is needed to provide adequate detection. Gamma spectroscopy must be carried out on these samples in order to distinguish the small but biologically more significant, particulates in the presence of the large amount of the dominant rare gas isotopes such as Argon-41.

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3. The stack-effluent monitoring system used is too j insensitive according to the Environmental Release Report i

of AFRRI. dated 14 December 1971. The sensitivity is' only 2.1 millicuries per day for eight hours of operation, i

or 6.3 mci / day for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 2.3 curies per year. Much larger commercial nuclear facilities have,often reported total yearly emission of noble and activation gases less

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than 2.3 curies per year, compared with 24.4 curies of Argon 41 reported by the AFERI-TRIGA facility, with measure- .

ments as small as 0.01 curies per year. (See ORP/SID-71-1,

" Radioactive Waste Discharges to the Environment from Nuclear Power Facilities" (U.S. E.P.A., October 1971, l - Table 8), attached hereto and marked as Intervenor's Exhibit

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"A".) Due to the fact that residential areas are located

- only a few hundred yards from the reactor, a much more

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sensitive system capable of detecting not only the principal Argon-41 buti also the much smaller. amount of theTfar more biologically serious activation particulates, fission gases as well.as fission product particulates by means of gamma spectroscopy should have been used. Furthermore, due to ,

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the low sensitivity of the stack instrumentation described, it would have been even more important to employ a series

[ of ambient air samplers surrounding the facility.

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4. No instrumentation was reported in the 14 December 1971 report to the NRC that would have detected beta activity from the ground directly, ihus, neither the film badges kept in wooden boxes nor the low-level ionization chamber were capable of recording beta activity in the environment (p. 7). This is especially serious since 4

no effort was made to analyze environmental samples for pure beta-emitters such as Strontium-90, which is biologically more serious than the gamma emitter Cesium-137 by a factor of the order of 50.

5. The equipment utilized for counting environmental samples reported in the 14 December 1971 report to the 14RC had insufficient sens'itivity. Thus, the multichannel analyzer had a point source sensitivity of only

-2 1.5 x 10 pCi/mf or 15 pCi/jg for gamma emitters such as Cs-137 or I-131. Equipment was and is available for achieving; sensitivity 10 to 100 times greater than this, for instance as was used by the EPA in their study of typical BWR and PWR reactors (BHR/ DER-70-1, March 1970, U.S. Dept. HEW, PHS, Rockville, Maryland). Since then, even more sensitive solid-state detector systems have come into widespread use.

6. The environmental samp1,ing as reported on December 14, 1971 was restricted' to leaves. No grass samples were taken, no studies of animals caught in the.

area were reported, no measurements were taken of typical vegetabl'es as grown in the backyards of adjacent benes, so that there was no way to establish the actual intake of radionuclides for the most heavily exposed members of the population. No milk samples are reported for dairy farms within a 5 or 10-mile area, which would have been essential to monitor both routine and accidental releases of critical isotopes as Iodine-131 and Strontium especially in the event of a serious accident. Yet large

! commercial reactors, sometimes with lower total annual g'as releases, are required to carry out such monitoring of environmental samp.les.

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27b. " Reasonable assurance" is that assurance which would arise when one who was fully cognizant of and educated l

as to.the health impacts of radiation and the capabilities and limitations of AFRRI's environmental equipment, monitoring and reporting systems would allow his/her children in utero, infants and small children, and aged and sick rela-tives to be exposed on a continuous and long-term basis to the routine and non-routine emissions from AFRRI into the air, soil, vegetation and water in the environment surrounding it. ,

l 27c. Intervenor has responsed to this Interrogatory in its Responses to Interr'ogatories 26 1 and 27a, supra, and 27,g, infra, and the same are incorporated by reference herein.

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27d. Intervenor has responded to this Interrogatory in its Supplementary Response to Licensee's First Set of Interrogatories, Interrogatory 27d (Docket 50-170, filed 8-2-82) and the same is incorporated by reference herein.

27e. The Licensee misconstrues the language of Intervenor's contention. Intervenor does contend that regulatory limits have been violated, and cites the sources and documents for this averment in.the language of the contention itself. See Contention " Routine Emissions I" (2), (3) and (4). Intervenor does not contend, to quote the Licensee's paraphrase, "that regulatory limits hav,e been violated and that such violation was not detected." That statement embodies an absurdity.

How could Intervenors know violations have occurred if such violations have not been detected?

This Catch-22 goes to the core of. safety issue l

raised by~the intervenor's contention, however, i.e., until Licensee's monitoring equipment,. methods and reporting systens are improved, Intervenor and the public will not have reasonable assurance dhat violatior.s of regulatory limits will be detected.

27f. Intervenor has responded to this Interrogatory in the Response immeidately prec'eding (27e) and the same is incorporated by. reference herein.

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27g. This Interrogatory is redundant. See Interrogatory 27c, supra. Intervenor has responded to this Interrogatory in its Responses to Interrogatories 261 and 27a and the same are incorporated by reference herein.

Intervenor further responds to this Interrogatory as follows:

A detailed, independently conducted epidemiological study of possible effects of the AFRRI-TRIGA operation on human health in the area surrounding the reactor facility is particularly necessary to protect the public health in the future since there is evidence that the area in the direction downwind to the south and south-east in which, according to the 14 December 1971 report, the

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highest aidxrne activity doses were expected and measured, cancer rates and infant mortality rates are at much higher than expected values'.

In particular, examination of the Monthly U.S.

Vital Statistics data published by the Center for Vital Statistics in Rockville, Maryland indicates that cancer mortality rates in the District of Columbia, only about two miles to the east and south-east, rose between the .

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early 1660's and the early 1970's by much more than for the United States as a whole, or for any other nearby areas of similar climate and population such as the State of Maryland or the State of Delaware, more than 50 miles away.

See Intervenor's Exhibit "B", in which this data is reproduced and which is attached hereto and made a part thereof.

Thus, whereas the cancer modality rate listed for the District of Columbia in the annual summary reports rose 22% between 1969 and 1976 from 181.1 to 220.7 per 100,000 population, the rate for the United States as a whole increased only 10.0% from 160.0 to 175.8. At the same time, the rate for Virginia rose 14%, Maryland 13%

and Delaware by 14%. In fact, the District of Columbia moved from a cancer mortality rate below that of New York of 187.9 in 1969 to well above New York in 1971, when this highly industrialized and heavily polluted area rose to only 201.2 compared with the District of Columbia rate of 220.7.

Although this localized sharp increase in cancer rates in the District of Columbia does not by itself prove that the releases from AFRRI were either partly or wholly responsible for this statistically highly significant difference in the rate of cancer mortality, it does imply that this possibility must at least be examined since .

radioactivity is known to be a highly effective l carcinogen, and since the monitoring of the facility was i not planned adequately enough to absolutely rule out the

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possibility that biologically significant releases did not l

take place. Only a detail'd, e census-tract-by-census-tract 8

study of the changes in cancer rates both upwind to I

the north-west and downwind to the south-east for the L:' period of time since the reactor went into operation couid "

I clear the AFRRI-TRIGA of any possible connection with thb f serious and at present otherwise unexplained rise in cancer

.,. rates in ,the District of Columbia. ,

The need for such a study before the AFRRI-TRIGA license is renewed for another twenty years is further indicated by the fact that the rise in cancer rates in the District of Columbia began some 10-12 years.after the reactor went into operation, which is ample time for many types of cancers to reach the end of their latency period. Furthermore, no large industrial or chemical plants came in'to operation in the area during this time, and other air pollutants such as automobile exhaust actually declined since the early 1960's.

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effects of releases from the AFRRI-TRIGA is further supported by the fact that infant morality rates in the District of Columbia have declined much less than they have in any other area of the United States, including New York City, Mississippi an'd Alabama with their similar large proportions of non-white populations. Thus, for the past l

l several years, the U.S. Monthly Vital Statistics and the I Annual Summaries show that the District of Columbia now has J

reached the highest infant mortality rate of any state; for ,

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reasons that have so far not been adequately explained.

Again, although this does not prove that the emissions from this reactor have been partly or wholly responsible for

_. this serious situation, prudence and a foremost concern for the health and safety of the public requires that a detailed, independent study of the geographical and temporal changes in infant mortality be carried out' for the, area of Maryland, Virginia, and the District of Columbia before the reactor license is renewed.

There exists here a unique opportunity to allay the fea_s of the public by the actual study of a large population exposed for a period of over twenty years of low levels of radiation. If some other cause should be uncovered to have been responsible for the unusually high local rises of cancer and infant mortality relative to the rest of the United States, then the result would be a great public service to the people of this country and all over the world where similar reactors are now in operation. And if indeed it should turn out that the geographic and temporal distribution of the cancer and infant mortality rates is such that no other source or agent can be identified, then there exists a unique opportunity fqr the NRC to correct and revise present radiation standards, siting safeP 74 monitoring requirements to insure that such situations e develop again for a possibly still larger popu-lation. the ultimate aim of the Commission under the laws establis ,ngress is to insure the halt and safety of the public, , resent opportunity to examine the actual health of a large general population group must not be lost.

Pending such a study, prudence would dictate that the facility be temporarily closed, or that at the very least equipment such as cyrogenic filters be installed to trap all radioactive gases, and that a carefully designed system or airborne activity monitors be replaced around the facility, together with a major upgrading of all instrumentation or environmental monitoring techniques to a level at least equal to that presently required for commercial nuclear reactors.

27h. Intervenor has responded to this Interrogatory in its Supplementary Response to Licensee's First Set of Interrogatorie's, Inte'rrogatory 26a (Docket 50-170, filed 8-2-82), and the same is incorporated by reference herein.

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INTERROGATORY 28 Answered by Elizabeth Entwisle.

28a. Intervenor has responded to this Interrogatory l

in its Supplementary Responses to Licensee's First Set of Interrogatories, Interrogatory 28a (Docket 50-170, filed 8 '-82), and the same is incorporated by reference herein.

28b. Internevor has addressed methods for improving Licensee's monitoring equipment and methods in its response to Interrogatory 27a, supra, and the same is incorporated by reference herein.

Intervenor further responds as follows: At a minimum, dosimetry such as that described in Intervenor's response to Interrogatory 27a.2 is necessary to detect radiation due to ingestion or inhalation. Gamma scintillation spectroscopy of air samples collected in restricted and unrestricted areas around the TRIGA facility is necessary to detect noble gas isotopes such as Argon-41, which once ingested present a

, significant threat to human health as Intervenor elaborates on in its response to Interrogatory 34a, infra. Likewise, l gamma spectroscopy of air, soil, vegetation, milk, food, and water samples in the neighborhood around AFFRI is necessary 1

to detect certain radioisotopes, such as SR-90, Cs-137, and I-131, which move through the food chain (air --Y ground --y vegetation---> food--yman) and are ingested by huma.s. See Chapter 46, " Assessment of Radioactive Contamination in the Environment by Field Gamma Spectroscopy" and Chapter 47,

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" Continuous Low Level Environmental Measurement of 41Ar and Other Radioactive Noble Gases" in Environmental Surveillance in the Vicinity of Nuclear Facilities, William C. Reinig, cited above in 27a.2.

28c.,d. Intervenor has responded to these interrogatories in its Supplementary Response to Licensee's First Set of Interrogatorigs; Interrogatories 28b-k (Docket 50-170, filed 8-2-82), and the same is incorporated by reference herein.

Whether or not a particulate monitor or isokinetic gross activity detector is required by express regulatory language is irrelevant. The requirement for said equip-men't is implicit in the regulations, quality assurance program, and ALARA principle referred to in 28b-k, since both are essential parts of any meaningful environmental monitoring system.

In reference to'the " isokinetic" requirement, see Intervenorfs Response to NRC Staff's First Set of Interrogatories, 1

l Interrogatories 18 and 19 (Docket 50-170, filed 12-3-81).

28e.,f., and g. Intervenor has responded to these l

Interrogatories in its Supplementary Responses to Licensee's l First Set of Interrogatories, Interrogatory 28b-k (Docket .

l 50-170, filed 8-2-82) and in its further response to 28b, c, and d,, supra, and the same are incorporated herein by reference.

28h. Intervenor has responded to this Interrogatory in i its response to Int ~errogatory 27a.2., supra, and the same is l incorporated by reference herein. Moreover, there is no l

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assurance that a gas stack monitor could detect radiation excaping through leaks in the staes or stack drain line such as that discovered at AFRRI and reported in NRC Inspection Report No. 50-170/79/10-11/01.

28i. As used in the language of this contention,

" meaningful evaluations" means quantitative evaluations.

28j., k.,Intervenor has responded to.these Interrogatories in its Responses to NRC Staff's First Set of Interrogatories, Interrogatories 14-27 (Docket 50-170, filed 12-3-81) , its Supplementary Responses to Licensee's First Set of Interroga-tories, Interrogatories 27 and 28 (Docket 50-170, filed 8-2-82) and its further responses to Licensee's Interrogatories 26, 27, and 28 a-i, supra, and the same are incorporated by reference herein.

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INTERROGATORY 29 Answered by Elizabeth Entwisle.

29a-d. Intervenor has responded to these Interrogatories in its Supplementary Responses to Licensee's First Set of Interrogatories, Interrogatory 28b-k (Docket 50-170, filed 8-2-82), and the same is incorporated by reference herein.

29e. The public record does: not contain sufficient information to enable Intervenor to respond to this Interrogatory.

Intervenor therefore reserves the right to ask Licensee questions on this point in the second round of Interrogatories.

29f. Intervenor has responsed to this Interrogatory in its Responses cited in 28j.,k.,. supra, and the same are incorporated by reference herein. ' i INTERROGATORY 30 Answered by Elizabeth Entwisle.

30a. Intervenor has responded to this Interrogatory in its response to Interrogatory 27a, supra, and the same is I

incorporated by reference herein.

Intervenor further responds that insofar as Licensee's concentric cylinder set model-is based on the movement of a,ir

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in an ideal state, without allowing for ai*r pockets and uneven air flow, and insofar as the model fails to account for radiation doses from ingestion and inhalation, it is unrealistic.

30b. Intervenor has responded to this Interrogatory in

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its response to Interrogatory 27a, supra, and in its Supple-mentary' Responses to Licensee's First Set of Interrogatories, Interrogatory 28b-k (Docket 50-170, filed 8-2-82), and the same

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is incorporated by reference herein.

30d. 10 C.F.R. Part 20 and Appendices B and C thereto.

INTERROGATORY 31 Answered by Elizabeth Entwisle.

31b. To the best of Intervenor's knowledge, information, and belief, the only public record of this incident is the Inspection Report cited in the contention.' Said Report does not disclose the amount or types of airborne radio-nuclides discharged during the leakage period. Like the Licensee, Intervenor would like to have this information and therefore reserves the right to ask Licensee questions pertaining to the incident.in its second round of Interrogatories.

31c. The fact that the leak went undiscovered for several months and was at ground level, approximately 28 feet below the required point of discharge for dispersion and dissipation into the atmosphere, creates a prima facie case that MPC limits were exceeded.

INTERROGATORY 32b Answered by Professor William F. Lankford of George Mason University (Phd. in Nuclear Physics, 1969, University.

of South Carolina).

32b. The analytical answer to this question requires more technical information than the Intervenors currently have access to. We need to know in particular the gap sizes that have been reported in TRIGA fuel rods with the age and history of AFRRI's rods. However, the swelling of U-Zr-Hx

, fuels at high burnups estimated to be approximately 1.2 percent to 2.3 percent d6V/V per metal at. percent burnup, (reported by M.T. Simnad et al in " Interpretation of Damage to the Flip Fuel During Operation of the Nuclear Science Center Reactor at Texas A & M University," General Atomic Project 4314, December 1981 at page 2-43) suggest a serious contribution to possible cladding rupture at high temperature.

In addition, a hydrogen pressure build-up at high temperature will contribute to the stress on the cladding walls. Thus,

's the combined effects of fuel swelling, hydrogen gas pressure, and fission gas pressure at high temperature must be studied.

If the Licensee or NRC Staff is aware of such studies, we would appreciate being info'med r of them. s i

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INTERROGATORY 34 Answered by Dr. Stillman.

34a. In the Licensee's own EIA data they demonstrate a release of noble gases that averages more than 20 curies annually. They estimate the public exposure based only on a whole body dose computed for a person immersed in a large clail of gamma ray emitters. This approximation totally neglects the effects of beta irradiation to the skin and internal organs. But even more important is the total neglect of significant contributions resulting from extended internal radioactive emissions. -

The cumulative dose of radiation administered by an absorbed isotope depends on the effective half-life, E, which is the relation between the biological half-life B, and the physical half-life P, given by E=

B&P There is reason to believe that the biological half-life of Argon-41, Xenon-t33 and Krypton-85, may be much longer than previously suspected. Apparently small quantities ,

of these gases dissolve in the pulmonary blood supply and are carried throughout the body where they are preferentially deposited in the fatty tissues. That-is, in partition coefficient studies, these noble gases prefer a lipid rather than an aqueous environment. This results in concentration

of these radioactive emitters in the fat pads of the human body, which not only increases their biological half-life (and thus their effective half-life), but stations them near the genitalia and germ cells (e . g. , human ova) of the body, where the radiation is apt to cause the most harm, especially in therms of potential teratogenic and genetic aberrations. These serious human effects have not yet been properly evaluated. It is, therefore, naive

< to only use the " gamma-cloud immersion formula" to determine total biological radiotoxicity (even with the " finite size cloud" approximation) and totally ignore the very serious consequences of internal body concentration and direct tissue exposure to th'e ionizing radiation. s 34b. and c. Without much more extensive investigation and research, only a. fool would hazard the quantitative guesses requested by the Licensee. For example, as these radioactive gases decay, their products include radioactive intermediates that have different physiochemical capacities for concentrating or localizing in other body tissues (such t

as bone and muscle). We have.done pitifully little research into the biological effect of radioactive

• decay products in terms of identifying their effective half-lives and sites of preferential concentrati'n.o How can we dare be more specific?

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- . 1 34d. We Intervenors heartily acknowledge the release of radioiodine during the Fuel Element Drop accident.

If we gave the incorrect perception, it was not intentional.

34e. Once again we verify that it is the internal emission of the radioiodine within a person's thyroid gland that produces its awful toxicity and has nothing at all to do with " submersion exposure to the noble gases."-

Please accept any impression to the contrary as unintentional.

34f. The ICRP guidelines recommend that the MPC (in air) of radioactive noble gases be based only on the whole-body dose computed for a person immersed in a large cloud of external gamma ray emitters. It is our contention that this procedure for calculating dose, recommended by ICRP, may sigificantly underestimate the real irradiation l

! dose because it totally omits any internal, :ellular contribution. We propose that the effective half-life, E, and the quality factors for the decay of these radio-nuclides in the tissues, (QF) cell, have been grossly underestimated for the gaseous isotopes themselves and their .

non-gaseous radioactive decay products. Unfortunately, there had been little research done on the radiotoxicity or Relative Biological Effectiveness (RBE) of the incorporated

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the ICRP conducted their last evaluation for the "new 1978/79 guidelines." The absence of truly appropriate studies continues to this day, five years later. It has been the history of Health Physics Standards that they consistently underestimate the radiological health hazards and have to be modified in the face of updated studies. . .

\

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INTERROGATORY 35 Answered by Dr. Stillman.

35a. There are at least three ways that the offsite release of radioactive materials can be considered a human risk and hence significant, namely:

(1) concentration of one or more radionuclides that exceeds the MPC standard (2) release of substances that are emitting radiation ) 1 m rem /hr.

(3) a radioactive release that could expose the public to a 100 mrem dose or more..

35e. In a TRIGA reactor the thermalizing effects of the hydrogen nuclei occur in both the pool water and in the zirconium-hydride matrix. If the PEA is associated with a significant elevation of temperature in both the zirconium-hydride and the ambient water (around the core),

then its thermalizing potential will be appreciably reduced.

This will progressively slow down reactivity (nuclear fission) by reducing the availability of thermal (slow) .

neutrons necessary to initiate fission. If the ambient pool water remains cool and only the U-ZrHx alloy warms up, there will be a lag or. delay (during which fission may continue or even increase) before the hydrogen nuclei in the alloy become too energetic to act as an effective moderator and reactivity (i.e., nuclear fission) is again inhibited. Under these set of conditions, the negative

= .

temperature coefficient is functioning as designed and remains a real protection. However, if the PEA results in cladding failure and the dissociation and loss of appreciable hydrogen from the zirconium-hydride, or there are major structural changes within the fuel elements that encourage phase transitions of the U-ZrHx, then these conditions are apt to invalter.'.3 the moderating capacity of the zirconimum-hydride matrix and hence the negative temperature coefficientmechanism may be no longer competent.

35g. In a Maximum Credible Accident scenario (described more than once in the initial response to the Licensee's Interrogatories) with a PEA capable of causing n.. Aple

~

s cladding failures at elevated fuel element' temperatures, j$ 1,000*C such that there are actual penetrations of one or more claddings, then all the necessary. conditions for an' explosive zirconium-steam reaction are present, namely:

(1) elevated fuel temperature }> 1,000 C (2) steam at the cladding-water interface (secondary to the elevated cladding -

temperature) -

(3) direct contact between the stcam and l

the zirconium within the ruptured fuel elements (i.e., water vapor will easily enter through the breaks in the claddings) l I _.

4 It seems to us that controlled experiments duplicating these sets of conditions could be carried out (without exceptional difficulty) to determine the explosive parameters of the zirconium-steam reaction. To the best of our knowledge, General Atomic Company has not attempted such experiments even though they are ideally set up to perform them.

35i. In a Maximum Credible Accident scenario (described more than once in our initial response to the Licensee's interrogatories) with a LOCA-induced multiple cladding failure at elevated fuel element temperatures JE 1,000*C, such that there were actual penetrations of one or more claddings, then all the necessary conditions for a zirconium-air explosive reaction are present, (1) elevated fuel temperature }b 1,000'C (2) air (or oxygen) at the cladding-air interface l

l (3) direct contact between the air and the zirconium within the ruptured fuel -

elements (i.e., air could easily enter j through the breaks in the claddings) l .

I

e.

~ ~ - ~ .

_ 33 _ .

It would seem that controlled experiments duplicating these sets of conditions could be carried out (without

exceptional difficulty) to determirie the explosive parameters of the zirconium-air reaction. To the best of our. knowledge, General Atomic Company has not yet attempted such experiments.

4

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1 INTERROGATORY 36 Answered by Dr. Stillman.

36a.3. The bases for this contention are dealt with in the detailed answers given to Interrogatory 26, particularly subsections c, e, f, i, j, and k. Please refer to these answers.

36a.4. The ALARA principle represents our government's commitment to minimize public~ exposure to hazardous amounts of radioactivity. If, indeed, AFRRI were dedicated to fulfill that public responsibility, it would not have violated the specific regulatory limits listed in the answers to Interrogatbry 26, subsections c, e,i, j, k and would try to remedy the inadequate radiation monitoring methods discussed in subsection f. A comprehensive environmental impact study could be most instructive in this regard.

36c. In the years 1962 and 1963 the maximum annual exposure at perimeter stations 2c and 16a respectively, exceeded 0.5 rem, the annual federal limit. Occasionally, -

regulatory agencies will inspect the NNMC grounds using an ionization chamber to quantify the dose rate. On at least one occasion, the location of maximum readings ,

were partly in residential areas near the AFRRI facility.

I i

I 4

4 Note, approximately 50-60 percent of the area within a one mile radius of the AFRRI stack is, in fact, residential.

There were several unrestricted areas where the cose rate was 1-5 m Rad /hr. In such areas, many people would have received excessive radiation if they had been exposed for merely 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> during the entire year, or about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week. This is what we mean by " highly probable" areas of excessive irradiation. Please refer to Interrogatory Answers to question 26, subsections i and j for spscific identification.

36d. The d;se rates alluded to were determined by ionization chamber instruments, not the film badges at

\

the environmental station monitors. Apparently, these measurements were performed by an inspection team from a federal regulatory ~ agency (such as the NRC). The inspection was probably routine and was not requested or precipitated by environmental releases.

. INIERROGA'IORY 36g Answered by Elizabeth Entwisla.

36g. Licensee has misconstrued the question and answer referred to in this sub-Interrogatory. They have no bearing on Contention 5 (3) unless there,is a zicronium-hydrogen explosion.

Respectfully submitted,

/ 'aura McALu i

Elizabeth B. Entwisle Counsel for Intervenor 237 Hunt Road Pittsburgh, Pennsylvania 15215

. Office: (412) 391-3211 4

Home: (412) 963-9942 Laura Macklin Co-Counsel for Intervenor Institute for Public Representation 600 New Jersey Avenue, N.W.

Washington, D.C. 20001 (202) 624-8390 Dated at Washington, D.C.

this 8th day of October, 1982.

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RADI0 ACTIVE WASTE DISCHARGES TO THE ENVIRONMENT FROM '

NUCLEAR POWER FACILITIES s ADDENDUh!-1 to Billl/ Dell 70-2

~

Joe E. Logsdon and .

Thomas L. Robinson Surveillance and Inspection Division OCTOBEll 1971

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U.S. ENVIRONMENTAL PROTECTION AGENCY Office of lladiation Programs Washingsor.,1).C. 20160 G

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1,674 341.8 aC4 143.1 444 101.1 241 64.9 120 27.3 ,

Pass aannette - - . ,

23,437 428.7 13,561 133 1 S,tS4 133.6 t,6M 43.1 9Z4 14.9 g Phc.se Isle =1 . . - - 4,010 444.4 1,ete 230.1 753 44.0 354 38.3 1 43 15.4 g Cere.eetica: 10,123 337.4 5,054 160 5 1,7t 9 90.9 3,u) 37.3 c1 .13.0 ,

p21:1a Atlett, 141,035 432.1 89,23c 233.7 34,9 3 93.7 15,151 41 4 7,C29 19.1 gev Y;ry 79,4 426.3 14,426 197 9 15,454 2.4 7,C SS 34.4 3,t35 17 me ,se, - . 19. n55 m.. u,m v3. ,m 8.3.7 2,9a c.? 1,n1 u.7  ;

pos:.sy.vas.in 52,a:4 444.S 21,145 193.9. 12,473 103.7 S,4CA 47.5 2,5 t 21 5 p IC"21 C'I:r !tA ,  ; [

gass :strts :satral is?,tts 3?t .5 . 64,t:5 111.9 41,0 $i 102.9 21,43C S4.t 10,t23 27.1  !

Cs30.- - 33,755 373.2 17,433 142.4 11,175 104.1 5,444 &4.8 t,gr,4 21.1 13tss s : . . . 18,993 3 71 .1 t,065 153.9 8,tC) 121.3 3,09J 43.4 1,443 32.9 lutu;s 4 3,1tC 434.1 14,738 148.4 u,uf 100.* S,115 90.9 3,tet 24.3 73eugu -

37,2!4 222.7 13,t:5 130.7 7,790 69.9 4,73 F S4.3 1,$25 24.0 .

bis:c .sL1 14,4 4 209.3 7,137 144.6 4,790 112.9 f,231 T,6.2 1,129 26.7 4,4% ;.cr.: ;e st s1.- E 3,711 373.7 27,701 171 3 19,l's 12?.5 10.441 El.3 5,C'p3 11.5  !'

yltr essw  :. 13,0'1 333.3 8,t37 117.9 4,257 us.1 t,171 13.1 1,039 23.1 I u rs.  : u,E44 Ca.9 S.C34 181.E 2,fl3 132.7 1 f 52 59.4 445 31.1 r Pa s a r.r t.- - 19,003 421.5 8,423 131.0 .

6,070 130.5 3,C '? 85.5 1,530 32.6 E4rtl : 3. . 1,149 b45.4 Sta 155.4 (13 102.3 c5 67.1 lee 30.6 ,

re4:3:e i . 3,t51 4C3.9 1,141 . * :.1  ?!1 ut.5 135 et 3 23s 43.4 i ht ra.a sA 5,740 3J51 3,538 418.4 1 1,177 124.5 91' E3.7 413 11.7 l Faz. ss.. . , 8,953 3 at .S 3,436 132 . 9 2 , 475 115.3 1,474 63.1 135 31.7 r s

57*"I

$*49, at te..ite .- . 104,417 341.5 42,025 147.5 f t,3'1 105.2 19,41? 63.7 9,5C 3 31.2 tolse 3,0C1 3*3.4 731 144.5 3{3 41.0 255 S3.0 123 22.2 Fary;.u:_ 11,897 3 42.3 5,S53 134.9 3,530 GT.* 1,753 45.4 918 31.7 tistries ef Coldia _-. 2,9CC 3. 4 1,445 151.1 E15 47.1 454 54.9 140 17.5 V1r41 tim- - -- 14,325 335.0 6,139 131 .3 4,253 91.1 t,87J 41.7 1,2 15 25.9 hoss ..rgi_ta 7,872 4?t.9 3,CM 147.7 I,146 113.5 1,14 E4.3 53t 23.2 krv *eall.a . . II,C33 3Ct.1 6,157 114.1 5,!!4 134.2 3.D t (5.3 1,779 24.2 kuts ;mes'.1ra 9,tti 3:5.4 3,1!S u?.2 f.f t? 103.7 1,v31 68.1 9 60 34.9 >

C4c rit e - -- *- 13,143 271 4 SelPC ll? .S S,718 124.1 3,t!! s a.7 1,754 3*.s  !

Tis s t fa - 25,157 414.1 12,743 I:C.'s 4,0't 137.0 4,404 43.5 2,144 34.1

• test cos'* re: rsi 41,154  ! J.1 18,973 144.0 1:8't 117.2 9,13e 71.4 4,647 35.5 '

rent.s o 12,944 4X.5 S,021 153.4 3,913 122.4 2,401 65.1 1,0C4 31.1 l Twunn - 14,tt ?  !!*.3 5,721 143.4 5,112 111.3 2,51, 43.1 1,354 34.0 ,.

A;u sea-- 11,M4  !!4.3 4,44 137.5 4,145 12 5.9 t,430 73.4 1 ,1 30 34.4 , [

Pise :J '.;f.*-- . - - . 7,647 2:4.2 3,274 139.1 3,C 5. 11L4 t,C a p 44.0 697 3#.0 g best f a Coitral 42,176 215.9 27,994 143.4 20,179 134.0 11,913 41.7 t,204 . ILS ArrA s u - 7,724 33'.3 3,157 151.7 3,7'3 137.0 1,4c4 73.4 641 22.1 b In ! r : e.ra 12,E;3 334.1 1,431 143.7 3,t:1 34.2 2,410 89.7 1,157 30.9 f eg: a 9,7J3 311.C 4,114 144.1 1,17s 123.9 1, 713 84.7 447 33.0 e

e ru.. -

32,tE4 ts.1 15,142 133.7 10,725 93.9 7,0 33 43.3 3, Sal 31.s [

b 4TST (

i b

P sui- 11,152 213.7 9,943 127.7 E ,190 77.C 6,*.91 73.9 3,103 34.4 1 ter, xa . 1,197 Su.1 1,04 149.3

• 723 ( 104.0 (33 98.1 333 eg.3 k 3 te: .... - . 3,De !05.9 921 129.3 (*1 93.5 57 32 .5 197 43.0 l Syos .a .. til SM.3 4!4 1 13.5 2 *0 04.4 363 107.3 193 (G.9 Col: r s *: 4,C l3  !! #.0 3,t?? 172.7 1,t!1  ?).O 1,233 es.S att 29.9 @

1,934 134.4 1,313 1:1.4 519 sc? 491 43.4

• 2., , f e e t t o.- (2.3 91 2

=** A .ia er s - 4,!st 257.4 2,253 134 1 1,135 73.1 1,244 74.3 (9? 43.4 5 gic.. . . 2,194 110.0 til 92.0 , 4%S 4?. 7 401 $7.5  ??S 25.4 2.oain = -

1,1LG til. 6 (21 133.3 34 75.7 .:S 47.! Is7 40.1 h:lfi - * - - EleUl 212.7 79,44? 149.1 24,1 % 93.1 15,9:2 n.3 7,t 99 19.1 I

, u'. it i". . ... 11e'* 4 541.7 7,19 ltL1 ",3N 93A I,059 10.1 97 23.5 I Creg r- 7,7.C  !! 7.* 3, t if 1(C .1 2,42 1 111.1 1, 93 4 af.1 713 31.1

, ,1 m rt : s. ..... G,ul ht .0 t #,152 14,.3 1s,19 P .2 11,1 % (1.1 5,4:4 24.1 A .t w . -. ... ---. 21 DM D9 KO 73 13.9 Sie 1.13.1 11 21.1 a ,. .. 1,E 3 1:4.1 744 33.7 3et 45.4 34 33.2 134 15.9 l

U DWCW I

1 70 a>

c 4 7^

MONTHLY VITAL STATISTICS REPORT 9 L .] '

o n ,i)

= ..

• 7 .,

Table S. DEATH $ AND DEATH RATES FOR btAJOft CAUSES OF DEATH IOR THE Uh'!TED STATES, EACTI REGTON, DIVISIO!(, AND 6' TATE. BY L COthR AND SEX FOR THF Ch*tTED STATES: 1970 g.

[4r rta e r r, a n.e.ev. hefern e% to res'.. at 6:stF.e see rring wm ti , t' ' ed re nt e . tw t se, fet q e,.w. n.ees per le* ,v e.wevenee r g ne:nsum J

• e a *. e . 2 - . . - e 4. - a i trea. W e i r r * *I *. e s. . f &,' .s'. .=L. , e.4.r rs ..f S t.e Ea g;tiu. f= 4. es.o., litete.et t.sr.el Classifiestlan vf inteses,

,/

4 6. . . . . aj p

(

n.1 yse .s e.sm, e . . J Es.4c.. . r .,f Aew1 e I t 41 res- emene.1. .a ,,,,,,g,,,m gg g ,,,gg,,g,

,, ,gg,,,,,,,g,

"*****'4"-* (*-N * **"$* ( ama+.23; l

c . r, e ra, t :

M.'f' . . ten,*iY,,y *.*. . g,h I l u

I e a im.-r n.t . n4 er e. ut e r si.t. s.=ser rate sine er ht. L 2 N

m.nc  % ll im od neie. 7ss , -42 n2.s .4...  :.w ,i u s ol .. u s .ss. ss.4 St .ss3 n.9 q

+

me-ree.le 41 , . .

317,ca ee ,1? t Su.

31..s 374.s l 1e,m it. ..P ts 4+,n2

.c.:

m .4

.w .e 93 es.

113,710 94.s los.o 72.m S t .naa

.o..

33.4 39,274 15,sf 9 2..,

n.7 d s

(

v3tte 19:,te 1 04., S r.a so s4.s 47,3as ;6.7 w, 4 '4. 5 93.s r.c ,9= s 77.3 33.1 m,.a i.e.- ,a, ..%.. ,u.. t o, ,9 ,t e., ,i4,.4 n;.. n e.t.7/.x.s w,2,4 13,s7,1 1 l ot.. n.1 u.. 14 l'1. ottivt

'in te-.

ist, il 3 7,8;;;

2 74.2 3D.2 14,2g9 19,442

??a.4 l et .1 24,124 A 2, 59*

j a;.4 1 01.6 17,50s 12,8MO 44.4 3Cf. 0 7,345 S,403 gg.g 44 .3

,.j l g

'et ai e 14,! 96

• t i. ? ;3,743 St.5 II,*s : 24 L. :n 105.5 4,7'e letta 13.9 0

<i.,. h k m. s.4 . I'.,* 6'. 9.4 f t,9 7 l .7.. 47,143 96.3 te,871 42.5 9,110 14.4

&+ '

a . . '

• ,7 37,.s c , ."';

• e . t. . ', t ','.47 106.4 Sh6f4 S4.2 14,912 24.4

r. r -. .1 %,51 ' 543.0 if ,ti? 11.t . *i #9,121 110.1 41,476 64.0 20,140 32.4 W .- t ag , a g .- 3 34,c 4 , rll f 343.4 n,7;p gg.3 31,,701 42.7 10,271 k?.S " '

m.

bau t, =.i . 4 f ,'

• i C. A 9:3.9 44.4

- 4,] . e 21,. 4 11,8L te,E87 2,119 j f.9 to. tw- - . Gr?. 4. n.9 3,Je t 1**', 4,414 114.3 S49 b4.0 3 Me 3 4.',

o . .... ../t. El. f 3,VI H J. 4 f 4e l's.s 399 S4.1 199 15.1 th e ls.s....e .

7. emci. 4 , '. Sam.;: 7 14 14 *.. ! 421 96.7 120 49.S 94 21.3 h w. ate. r. . . 4 t,18 467.3 V,1 4 6 r0.3 f ,7 ta 15).3 i, Cit 46.3 973 5 8.d k, Kmto 1,.s . . . . . - - 1,s e 438.4 1/W.? 93.4 I , .n e t easie See 36.9 '$n t1.? L,a r+n. 4, c ,3 . 1 .,34 334.r. r,4s s e' 7. 4 k ,747 9: .9 1,125 37.3 479 15.9 6 hic At uint .. Ls ', % 42L 7,* f. 4 4 3 95.3 5,ble 41.7 6,991 i%9 6 #,- ,,, 4,4. 5 c ,m' b.ut.

i 3.i 2 u,4 4 Do.s 6,ws se.3 3, ace i7.,

9% c . .. g . g J,*.w 49.7 1/,151 1 13.5 (,31e 84.3 4,994 41.4 1,115 19.t ',

tews. 3 s e .' = . - - - S2,M ' 44!. 3 41,:7.1 1.r.. A 2,t

• 107.) 3.,527 46.9 2,40m the J. *'*1 fl*1W' t ert a rgs *.r r : s;  ! ',d e. 3 sti. 7 H e 'id ' t. .t 3 9 , '/11 51.2 9,9A 3

.',',4dt' t )

24.0 j 4 -

's,e  ? N.1 1.,8 47 14.9 193.9 ts.f t,,S I S S1.8 3,609 34.6 m

.. 14, t 4 'Ss.4 *i.( W. 9 a.,14 7 11*.4 .:,'tst SE.4 34.9 R ef SS es. 4 ;,r: . e 4; 9 S*) . 's a.'.e 9, XS !s,*. 7 . .'>to 44.4 3,431 31.9 [-

. .. -  ; <,4 3 as.4 1 , c... -i., 1,9 .i; 4,447 s,u.t 3,asie n.7 k .l ne w 4: . . .,

,.'. t

.3.s'F.1, d ,1 I..., lt

. .e ,. 3 104.2, 4 9 i.. .,329 f2.2 1,093 34,.7 . N

. . .. , . . . , . = . . . . . . . . . r. b: .. m. . 1,.. 1. 4.94, t s.,

ry

. . . . . . . 3 4,4n 34 7.e e , '. 8 e . a 1,419 114.0 4 ,12 3 SS.e 1,035 3 .!

27.3 * 3s t e ,r: ' .? s t" . .. -,r% 1,737 41.1

)h 4' , di 42 % 7 927 >

5. . -4 h ,' S ' w .

r. e- .

n, G n ..

%?.

81 1

,o t, i.e . i 1;i.4 t . .t .1

.',l 01

• 35 n 1> .

18C.1 A g t,.4 3,mi 384 474 u.

54.0 71.5 i,432 182 32.,4 n.

4%L p

d,: e' . p '.?

24f. 37.r.

t c., s - 5,7 i 4 t.. e 4, 4b I #1.0 e , nei 134.9 973 65.S 447 30.1 Q[;

se . ... . . . . . 1, i t**.* ),% . N1. 0 118.1 61.!

. ,0 H i,373 $76 33 3

' 3 "'t a? 1 4. t . '. \ , L - 44 %t- 4 7,* e 11.6. '. LJ ,2 .6 t R,.2 1:',f2 8 C4.1 9,473 %1.9 pa tjl t .m : ,

4Nl S t.. ) .e: # 39 4 37.s es8.1 319 bC.E 1:,9 3.1.4 .a

8. . ........ * ,41 : I

• e .4

. .,%n l'%' ,! )/ 44.3 1,JM s 7.9 334 31.C '.

• e < ;i,,e t ! . -

T,3 he > 64.* 1,'s :4 .*.* '*1 IM.it f.24 69.3 til irg.* \

.e.' 4 6,t '9 f [g,

. . . . . . . . . . . J 18. 7 t ,?' l 1,' ? ' 6A.9 E sti39 t#..# 1,21fD 18.0 e

..tv..,... . 7, -

4 .e ...z. 14.4,

,r. ui.. i ,24 i F1. : s37 w.. -s'd

< > r .,c.,w ,

,, r , ,, m.r ,w v... .:,u.

. . .?. u r... 3,u n.= i ,7= 3., "I.i  !

4, 4 n n. a,au i o .. . ..w 3 n o.i 4,a <e 73.a 9ar nr.3 g

..s - i s,: . m. s . , s.i m.:. s,r 4 4 its.e ,344 r%7 t ,7,4 v  %

ri _ . . . gi ve.$ 397.6 IJ ef ed ddl .% 4,44* 124.9 4,419 Ste.1 2,109 31.8 4 / u. /, 4e,9 %C'.0 1 *,.*/ 8 Ibl .1 1(,C'93 b

a . 130.4 9,211 71.9 4,7' tit 55 . 4 '

h...n,..... 14 %: 4 34. 4 t ,2 '5 s e l.. ',W1 1d%1 3,21G 69.5 1 ,04 6 n,.a o s.

• 2 . 16 g

s e

. . . . . 9 ?4,.

e ,, ,, gg7,r t,- a t t.

,m9 4,.47 ist.7 g ge ,q r,na 3,f 77 e4. 7 74.3 t , us, 1,137 s;,..

.v.,.e ,, pq 7.. :q g ; . . . . . . . . . , , cf . 54*.. t ,. i1 3, 17; t?$.4 1,91 0 St .6 923 4 : .*

...a,.r.t........ sc. - u , ..'4 m r,m ns .4 .:.

net wa r ...

c,.gt .ex ?

• ff*

• e 14 7. A

,,An 1,%%4 n.3 f.J.4 e ,ie.1 634 '

I i

L.e 44 M1.1 ..f

.. .. . . . . . . . . . . . i;,L t g,s e ,4 . 5 .e . . ,t v 95.4 2,473 rwg 1,174 gg

.%+., f.h . - t 8, .e 6s .,'l* -

6,736 f.7.8 79

• j m ., n ,.s.: e i ., u 1/9.-,

9, . 4 7,w, c3.1 3,s,1, u,.

r .i 7 ',3,.,

.Y '

.e. c ,me.

. . . . . .. n:,w , .. . i, a.. .. .., .

ir,a i,v

~,. .

(,3s4 7s.S

n. ? as .n1.1.s 3.i35 9c

37. .

42. .

@b g'

.. . . . . . . . . . . . .", 22... 91

• 152.. &7 $91 M2.9 313 43.9

.... . . . c 4.. ... m R.L 9.. E v.3 170 9 t; q

m,

,7 .,

i.

,.. . . u. s 1.%..: a t.9.4 s*

4 ,, .,y on., i ,m .3 s . . . .

2 ,e t , l g y;..s.

t

. 1,'U tae .- 4) 8%9 91 89.1 477 of .9 3

. - 4,'t " i Efd.7 . , *.e i t44 - t ,'414 74.4 1,445 fr.o 709 40,0

• • .I.j, 213.1 . ,N T 9'

. . . ~ 4,d' '  % ef 3 52.4 517 f.e . 2 3?S U.", M t . . t, l ..e RSP.4 ,'.s $ LV., '.2 7 44.9 3C5 74.7 19% 4%S 6 f .- sto,t.so W.4 t i,7dt4  ; 4, %A4 4S,A10 $9.3 7,136

, t? r i 91.9 16.9 y

. A..gt e. - .. 1 1,18 ' 327.4 .

• ,.1 J 1:..

• 10).3 u,046 en.0 921 27.0

.' .W . 19

,4-- .. 7,1 . ,

34 2. r- 1,41 s e' ' E 11 % O 1,9&I 44.4 728 94.A M e; gi. ' 534.3 N. 7 F,*4. 5",'34 10 1 I', '93 11,f 32 Se.

• n 246 24.3 y

'st- . . . . . . . . . . . . . W 97.3 177 . Mr 29.3 3S4 117.8 l@ 3%c y

==. .. ... 1, L. 186.? F34 S.. '94 5%c t ?C Sb9 13E 17.7 "'

y_ _ -~_n

.m

__a -

l l

~-

- m s a,.

~

.-_--_n_ __

~-. -. -

e

. . +

.1.......~. . . . . . . . . . . . . . . . . . . . ..- S- d' ** * ** *' '

MONTHLY VITAL STATISTICS REPORT

• 9 tac., S. DEATIL$ AND DEATH ltATE5 FO't *. WOR CAUSE5 OF DEATH FOR THE LTNITED hTATLS, f.ACH ltLGION, D!VI.JON, AND STATE DY COLOft AYD SEX IO't TifE t; KITED ST tTES: Igt!

e 6* r.1***". 9*f", e ty to res te *5 tw. e atmtes titr $

(6v It O. PMrsn;em trivan :vr'..e4 t f #c mee4 at We er,t t te L'r.ites.:  ; ry s. nes..? gr.,ristes La

• s .es n .v.t. jfett!

,,t s f.stH.

st, w e o. see 1,*,y) e sttgstet pggstst!,.

vi- n. ' w]

. .m; ;,,rs:t: tunes of r,tsmes,

_ _.m aa.=:-. - - - - - - - -

~

a smilc....t seerhau tie asn et tes.s &c.etutrc te ptu s ,

e,tenrere*evise m,,, .e., ..e e,ee N'

• Der eg,,.,,o tEs es 1.sena. ( 49. s!si A: .se t *.ea s O m m3*

reser eet:42, scrisme (seosaad me, . .t o 3 ,e, ,,,e >.e, ,.se t

z e, ..  :: e, .,

t, t t . , n e , e s.._ ...... . . m,3 . al.. u ,, m uS.t l ,,,,m m.3 r_ , ,3, .4., ,e.,,, ,4..  ! .

.,i e.. -

en.n4 .u. , io..., m.t .4,u. .3 , u. ,,..

Fessle.. 3*3,(32 2*A 9 123,521 1:3.t 114, t! 3 19..!4 1:,14:

S t.n, ,4. ,  !

Att e..-.m .. . 473.241  !?;.6 331,952 Hl. 3 33 3 13,t:4 14.7 19!,115  ;*1.*

s*)e.... Is!,314 437 1 143,914 394 3 87,149 92.9 E,*.t3 41,t:1 12.1 47,043 24 0 hr. ele.. 231,997 313. 7 139,334 14 3 33,441 37.9 9 149.4 131,437 133.7 33,434 22.9 e

1. 21 other .......... 59,3?! 157.9 31.444 134.9 15,139 I.3,c2 34.7 Fale-. 37,930 95.5 11,274 44 9  ?,13e 26.3 3 73.S 13,941 3.19.7 12,2,1 34 9 tt,ata Fee nte.. l'axg g,434 31,473 737 3 33,493 115 6 13,444 EM.P . 43.3 4 t:0 33 6 3,p:t 14 4 D*e'e.s e 4

f. ,r .,t . as .. . .. . ....~  ?*4,tS6 415 9 92.972 19?.t 47,l'7

• 7*.1 22,921

!crtsCesta1* ~. .. = ~.. ~ 214,743  ??6 4 94,339 41.8 9,t31 33 4 144. 9 43,904 3Ee Sc,t'4 f t.7 3s,37 .. . . . . . . . . . . . . . . . . 713,n!4 337.! 93,53h 154 1 43,619 to,t:s 39.9

..s'.~.....~-mm-.-~ *% 9!9 IS$.? 43,615 9 4. ) 3 3,q?g 31,9 3

379 4 11,321 145 1 31,632 4 7. ? 11,4:1 fr%? t,ps4 33.0 6

!*.F"r.7.AS*

i.e, g .41,s t ... ... . . . ..... 41,*19 394.5 t?,073 1 91.4 11,f 24  !!.9 S,?47 44 4

!*s g r e. . .. .. . .. . . . . 4,3 p 7 4es 4 g,948 H4.0 1,131 1* 4. 0 nt 7,133 *a.t

e, y..rp? t re .-..o ..o. .-- 2, t 3 9 3 *f . 4 1, S? ?

35 3 t st t4d i,

yo-;.t................ 157.4 *H 173.9 ff.  !!.8 M3 i 1.111 I".9 34 D3. 4 19 8 tres a t t Nr *W... 23,3!! 33,'97 41 1 8 9. ? . !?? C1.? De 15 0

. . .....* 4*-).S 0 393.1 '

lei 1* 3,4 ?4 4.349 471.7 1,t23 If.1 48 4 4t2 17 1 P.ude err o r i !v.~. s.t e !..-+~. .~ ---..-...-~ ..-. 13,14) 32h1 178.1 804 M.f 3/4 !4.9 1st

• 12 0  ; P

.. ... ... ... 15),773 f , tt i 14 1.4 1 '33 S t.T 1,1;3 27 4 Sn 14 5

s

t,ile p;,v.t s. 411.9 70, 61' 199. 13,(f t 94.9 M,!(a '

, Terr.. . ... ........ . Tf,1s3 4 D.1 h,!*T  ;?2. "

41.4 7, 339 16.7

'... t e r: ej... . ... .. .. .. .. f ),5 41 14.44' ?tf 4,7#' 27 4' 3,tse  !?.4 4L1 13.134 h?.1 f,2!3 87 3 I,M 4 in". tear;e.~..... .. ...... .. f !,1! 4 441.1 197.9 e, 84 0 8,983 19 3 71,312 12,4t! !4. I,!!3 f,451 44 9, 33 5 e

.n erm i _

1

. . . c...co . . . 1... ._ . . . x,,,, ,.4., ,, ,, n a ., i 43,4a m.1 =.u, t o .~.. . .. . .. ... .... 43,344  ! ?,4 0*

o., -

,,,, ,4.,

3 't.t If 3.4 D,f t! 100.7 t,!:* 4 *.* 1 P,Et

f

w.................. M, '* 7 iti.1 4,1? 1 l' t.! g 4,387 13.t 1,X1 2,f b3 21.6 4 7,* . *

! 1;; t e r ; , ... . . .... . .. . . .... .

4*1.1 e4.3 S3.1 FitM fvm ~ ~ * . ~ ~ M,7M it,D! *11.

. 4 11.Mk kr. P 1, ?f f 47.7 { 2,1ST ' f* . 4

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MONTHLY VITAL STATISTICS REPORT 9 2.w, >. .m n.J e e, m wn ons a m..a ro a mm .w, 1:n u:m, emw,:; ,a swo ,.r co:m un, u.::

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Th.! sed States == 725,- a 343.0 245,511 136.3

• 13,M4 102 .% 111,544 23.4 Se,3M 27.0 Mele t!4,534 418.3 114,4 r6 18.7,.7 $6 St.J FS,ts! ggA 3 34 33,g Treal. 331,E3J 3D.3 137.144 117 A,M,4 112.5 33,4 4 34.4 43,0 1s, sg L.>.1 sh te . $$4,3S2 3 75 .2  !)3,9 34 (j,R7 l' s .D 197.!v, 1:3.1 tr.it t $4.3 4a,74 4 2d.4

'n hie. So3, t'Ja eh.1 167,679 5.I.7 $3,310 $3.4 47,173 75.4 34,$rg  ?,3,3 i F.r.J.e , 159,550 321.0 161,534 jut 114,153 112.0 31,' J6 33.4 14,109 1s.3 8 A* 1 er.P.er- 71.482 371.5 34.332

• A >s.4 25,954 $ 9.7 1?,7?t 63.4 7,S L4 24.5 +

Pale Se,434 M4.4 23,7M ( 15".1 12,173 e4.6 12,972 97.s S,42e e s .7 =

f ra-le 237.6

• 3A33 13,534 . 113.4 13,4A 1C4.6 4 / 13 23.6 3,t44 13.7 F es!.*.d e

• pr :esst FC4,C34 414 .3 93,434 1M.4 47,513 93.S 23,5 3 41.3 13.3 9.224 br;.a Costiti t?3, A63 343.4 54,h1 117.4 61,f 44 107.4 2 3.{ .*4 53.4 16,HO 24.1 .

Sn.t -. 22.,256 344.7 1;3,dtts 13s.6 72,3t t 311.* 42,2;2 shot 21,154 2J.3

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3re 1:44 . . . - 43,073 373.1 a t ,4 M 113.9 12,*ss o p.4 5,124 45.0 2,t*4 13.1 P.. se . .- 4,6:4 458.9 1,624 117.5 1,D4 115.5 Sht E4.s Sta 21.4 F. 3r,stLa w 2,787 234.4 1,461 ild.S f r3 116.0 543 45.0 163 23.1

• i

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>?.t1*e stiv. tie . 133,144 415.7 71,104 149.3 30,4*4 ' 56.2 13,153 43.1 7,031 14.7

.v ' siw. -

77,C34 417.6 14,653 1M.3 15,4!3 83.7 6,4% 37.7 3,212 17.7 .

Sev .*.pM -.- . . 23,516 4!5.7 13,f f: 1 64.4 4,414 07.5 2,77p 39.7 3,334 13,g ,

e ter.;,ylmta - 53,215 447.7 22,572 1M.4 12,61% 1;5.1 5,M S 46.6 2,492 23.9 &

l'??"t Cl*7"?4 lu s *.r..tr. Cert e d 155,194 3M.4 47,474 1&3.4 41 23 ) 1h.1 Pit 49.4 D,424 21.1 ge;3- 40,464 577.1 13,4;e  ;.18.4 D S'S 1 :* .4 23[t34 f,

4 9.L 8,40 21.3

-4

e., 13,504 1:4.s 4,484 153.1 6,254 1.6.5 t,93% f.i .% 3,$ c 24.4 1.!!sats - 44,144 475.3 4 19,r.5 9 173.3 11,3;4 1 32.9 5,tal 46.5 2,3 ;4 ti.t I y: .:;fu _ . 33,3;5 333.5 14, N 13.1 1,333 93.7 ' ' 4,1 s3 ss.3 3,.%t 26.1 et e.. -s.s. . .m..... 17,El 3 *0.9 7,3 De 153.3 4,$14 1*T.S t,3!! 51.3 4 ,82 4 25.9 4 c. : ru a.v r t1 . . . . . . ,,. 53 18J 332.1 83,846 174.7 23,4!4 113.3 1* , S's 52.4 5,L18 33.9 Paz.sa.a . . . . 13,,iEJ 337.* 5 ,2 74 141.3 4,413 1.5.7 ' t,tla 57.0 1,072 f *.?

3., 12,134 4 2 * .,9, 5,114 _177.5,, 3,449 124.5 1,743 63.3 923 33.3 yu n.r; - . . . . 33,1M 413.4 8,M4* 145.1 6,4to 112.2 2,634 61.3, 1,419 23.9 kr.t Ze:4ne _.

2,112 347.4 all 12 3.7 722

• 3.9 4 43 E7.4 134 33.9 f..*1 1a 02a.. .. 2,7 ;4 337.1 1,113 163.5 744 1;).4 7;e 113.9 3.x 46.7 Set tun . 6,016 f r5.3 t,7;t 177.S t,3.8 13. .? &at $ 1.6 4M 3L.7 1.a.ua.a 4,5M 383.1 3,912 174.3 t,522 113.4 1,1 41 13.5 694 Es.t

$* 1,~T

42n A 1.r.ste - 111,?44 344.9 St,'.63 143.1 !s,1 64 1*?.4

),254 s3 s 31,110 32.0 erm .; .. . 2,124 37?.1

• 494 154.5 4}4 74.4 754 45.2 3 33 3 ;,1 Ed.yl m .ad -- _ _ _ 13,145 213.9 f ,3 34 1$7.4 3,u t' $3.3 3,742 43.5 e;0 g ,.c O.stris*. e r C316 %* t . . . 2,152 139.4 1,SSb f (4. .t 712 53A 445 59.3 lit 14.9 7tr4Lc.4 _ . . 14,113 313.1 7,h1 *11.9

. 4,114 61.3 2,7&4 $ 7.5 1,121 :3,4 but Ytt;tr.te -- . 4,145 413.9 3,323 163 .1 t,1;3 *:3.1 1, 31 31.9' gr.? 31,3 l br *.h :ter f .o. ..-.. 14,674 33.4 7,C22 134.5 0,3.4 nn.2 3,f *D 75.7 R W2 35.3 2..*Ji C ir:* ta t - = . . . . . . 8,414 3.3.3 3,415 11 3.5  ?,* 1.1 A t,C*.4 74.6 1 C.12 33.3

'w rm.. -

.. 14,f M 3'.fe.5 f ,H C 134.9 S,54 3 115.S 1,344 7. 3 1,d46 3 3.g 7".*rtt. .. . . .. .. 30,f M 415.4 15,417  ?;S.1 3,175 1?J.3 4,6?S 63.9 2,4 4  : .3 I v* 't.tt Cesa.rsi 47,3a4 339.9 ti,4?J 157.1 17,tr 021 123.4 S 314 77.7 4,a44 SC.m

• e tt.py.. . . . . . . D,43; 4.4.2 6, C .*J ' h44 4, e nn.4 2,,; * . 67.3 1,111 33.6

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l 3u. u n:_ 7,m ut .3 3,u. at.s 3,2 .u.3 1,m .. m 42.3 j

l'est t.u.n ts2*r .1 . 55,514 317.9 3 s, s 41 143.4 t i,9"se f .4.0 12,tF4 C.1 6,40% 27.3

• Arn ns. 9,Ccl 393.7 2,43a 12.3 4,544 144.5 1,C S 75.1 734 27.4 r *a '. s t w a - -_

. 12 33 s A t ,77 ; .! ! .L 3,709 P e.1 2,374 65.5 3,DT to.5 f.d f.:.s 10,5*4

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.... 1,7); E n.4 Sc6 33.4 T,ssa.. . 34,534 2 59.5 14,7# # 144.I 1.,; 74 93.4 7,C 73 61.2 3,764 32.3 ES*

M: w. t w.s. .... .. 22,t 73 12%.S 12,742 1?2.3 8.51; TJ.3 f ,,,7 3 74.0 3,584 29.1

.~.%r.s...... 8,199 319.4 1,1 *J ',3 %4 fed $1.3 ft! g.a.7 3*1 45.9 i

. , .. ... __. I,tSt 151.9 vsJ 1s!.4 113 at.1 Ta 53.3 gw 31.1

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• a y.4 :_

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, W........... 2,4' 8 21s.. a,. 2 Rv 7H 43.S 7.1 (2.) . 34 3.1

! 5,.w......... 3,1;t 2MJ 7J  : s' .3 s t+  : .4 4* 4 74.5  :;s 33A

. . _ . . . . . 41,M4 3:3.9 4..'..' It ' .! 5% ,! . J3.3 *s,3 .4 14.3 , 7,14J 31.7

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s......,.......... 7,4 M 3 * *.C 3,! ' if '.

• 1,L . e 1;t.. 1,179 (1.6 73J 24.3 I i f . r- ; .. .. .. .. . $ 5.,2 9 7 .' . E 31,s.4 as. 3,*. 4 v? 4 11,s .4 ts.1 3,4 t; 24.7 31J s *. (* Td 54.o *n.4 is

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.. MONTHLY VITAL STATISTICS REPORT .

9 TAbts S. OXATHS AND DEATH RATE $ FOR MAJOR CAUSES OF DEATH IOR THE LTNITED STAT ;$, EACH REClON, IAYt3!ON, AND STATE: BY C01.OH A.ND SEX FOR THE IJNITED STATES: 1373

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P. aster lista Nat.t A.ie h,ater 4.te h e ee S.e,. pues,er pote 4 uu..a t.t.: 3, m .0 .. m ,.a m.3 us.m w3.i m,.u .3 o,m ..

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311. tat.r Den t.

374,070 F2,f ts 33,154

$ 71 3 3~ 5.9 34,174 31,7'8 143.8 110.1 38,299 12,E4 113.9 99.4 94.1 30,$30 17,119 13,614 22.7 64.6 99.5 13,t ta t,$30 6,371 14.3 to.1 43.S f{h gp .

7. rale 33,530, 333.1 16,300 11F 9 13,941 98.9 ,4,102 33 4 1,939 14 0 messe,si t.:t !

portseest -

• = . 3CI,431 437.9 94,149 190.0 .44,952 94.3 70,143 41.3 9,83 13 4  ;[ g porta Co.tr.1 = tif, Sit 3ff.' $ 5,908 148.2 90,4'3 105.0 #9,967 52.1 14, F29 33.4 e b soutp :- - 229,4n 344.4 1C8,774 100.3 74,134 113.6 43,054 63.3 11,157 f t.1 * #

• g.

bess ... -- 3 8,410 374 5 63,G4 144 6 33,1sD 43 1 St,0W 4C.3 10,423 33 3 I q

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. 46.143 391 4 22,423 194.2 11,999 97.9 5,'as 43.7 4,330 13.3 [V .

Se.eatre ta4NS

! e !".a,;s?1

. - - =

4,333 2,533 431.3 334.2 1,94 6 1,173 1 s 3.4 174.1 1,1H 411 us.3 101.6 54?

3 72 SSJ 46.4 33.

144 31 4 13.3

(5i vernera 1,713 349.4 8.4 175.9 4t? 91.0 304 64.4 143 14.5 l 3 a.sar.nette -- = . * * =

• 22,944 394.0 11,0*$ 120.4 S,144 94.9 3,MI 44.4 1,0s3 17.9, Fa de 2s'tal 4,C 32 414.4 3,934 199. 834 4E 154 g ,.

e 44.,1 13..g e m .n1,.o. 13,4a 34c.3 1,o, In.3 2,ut n. i,u 44,.3

3. m 1 .9 h 4 9'isc. 4tia-ste 134,c44 415.9 72,140 17r.2 M,M4 91.4 11,193 0.5 s,9ss 33.s 3r

.e, 2.rr .. - 74,* 73 4*4.7 13,445 164..* 15,7?? 47.5 f,444 37.L 3,c43 14..

bee Jersey -- 29,0ve 3H.S 16,0>4 1M.t 4,519 es.s 3,e47 31.2 t,321 37.9 l h(

3 Pewayit t:to .. -. 52,4M 442.1 32,431 IM .3 St,ul 103.5 S,440 45.7 3,ke 21 4 +

!) #

SG*N C7;fl3LL, '

!ast 3k.rta Centria =

0s13 .

• 153,510 43,121 375.4 377.7

$9,C33 1 !,443 1C4.1 172 1 40,'C4 10, 4 8 63.0 101 6 19,HS 4,952 45.9 46.4 9,815 f ,340 14.0 11,3

.j -

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llar,a t s - *~ 47,174 42).9 19,646 114.6 13,444 54.5 5,1C9 45.5 3,443 32.3 esg, Su n zign. 33,5C) 330.3 14.173 13C .2  ?,931 47.7 4,638 $1 3 t,tst2 15.t bs4:s st* .. 14, F?1 3-3.4 7,314 10..l 4,$H 102.9 3,30 3 30 .4 1,13b 23.3

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W.st Lor *.1: Oes .ra l. - .- 44, Die 343.5 23, *a: 7  ! ?I.5 19,9H 112.5 9,9H AS.O 4,914 19.4 c' 11, H 4 8,1 72 153 4 4.*15 104.4 2,1*0 54.4 1,34a 34.9 C 9ttraess% . 332.t . ' *

! >,s .. 11,t25 3M.f. 8,213 173 5 3,!aa 1!$.9 1,731 u,4 e53 ts.4 y;assari. 2J,1.13 4:1. 9 3,634 194.2 t,144 13 3.6 2, 741 41.9 1,413 33.5 l l.'ortr. Tec.ata - 3,2(1 333.3 943 144.0 437 104.9 399 62.3 313 34.3 l ,

Sarasa la'.r.a . 3,591 373 3 1,1s1 144.4 ?M 1CS.4 514 15.0 tse 33.1 g 1,944  ?*

144 3ep.ms e 5,4s> 349.9 2,414 114.1 920 53.7 425 27.4 8 IJ.uaa- 8,927 3 31.7 3,tsa 147.3 1,523 114 1 1,30 60.1 E49 33.4 MU 13,540

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1. i MONTHLY VITAL STATISTICS REPORT ,

- AND R THE UNITED ST ATES, EACH Itt.C30's, DIV! TON,AND STATE; b l' 3975  :

Tshte 5.15EATHS AND DEATH ItATES FOR MAJOR CAttSES OF D1;ATH . .. ,.... ,

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116.9 ,,3J2 s2.6 1,077 pp.3

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37LS 4,9%S 3,944 ,L5 rus..wentro .. . .

2P,751 34,144 3 37. 7 6,057 5,c27

'.'.".14 3:.7 T, 36L 2 4,19,) 11h3 313 3 1,539 67.7

$8 2 486 S,467

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.tr M6.9 e,tas Jaeg 93.3 1,,s:o,275 Gat. 0 969

• 731 2b6 P8.3 J

Pi ss' e s tp;!._ _-- 3,441 59. 3 We st sa ath Cen ",ral .._.- _ .

t,ns Sn 9 6,141 *t M24 1H 9 3,6t*7 3,41f 37.9 32e. 3 3,034 6,932 $%6 4,=.r......_........... ... D,444 4,044 10,'?4 47.5 1 t e t er .._.-....__._ D,261 374 4 11,915 ".11794

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,,931 3064 r' t. s a s ...... _ .- - - 5,930 SL3 pr.a 3% s 6,549 Es.O 17. 0

%:ST 377J ses 592 Rs4 34.9 23L1 12,373 554 LSD 64 0 43 9 PP,773 1,7*8 344 4 s%S 354 29L O IS%7 771 313 e1.7 610 217 Pa si e .t n..... ... 9,177 1,11) 't?.1 .S2.3 pun ter, s .._.. _ ._. 372.4 179 9 1 77 42.1 1,326 471 4L 6

. F.314 446 1,S74 , 77.0 3,t154 374 3 A2b 3, 57,8 . 893 s >9 So.S J es% .._. . . . 234 1 3,073 643 ' 57.9 22.7 vjm34 _ _._ _ _ __ _._.-- 5,t31 F,filS 1?$. 7 3,316 ,ut.1 1,454 4: $ 3 ,2 87 84 StL2 274 306 9 Co.l.,61..........-....-

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1,144 144 5 9%S 110 434

$4. 9 01.9 3%

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l te4%............ 3,399 45,314 3&% E e Seit e1,344 2nd. S 1605 3,184 l 6,L 4 1,P" % 6,520 PL3 n.nN................ -

% 5,n?9 2,3 37 1 3 .1 13,9?? $1.6 34.1 *J.

. ..-_ 11,C12 S 144. 0 320 l

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.e MONTHLY VITAL STATISTICS REPORT 31

,=-e .e e Tebte le. DEAT7tB AND DEATH RATES FOR kt AJOR CAE'St S OF DEATH FOR THE L'NITED ST.4.dS, EACat RECtON e DIVlilON e AND STATEt AND BY

, COLOR AhD SEX FOR THE E'NITED STATES: 1976

, l ee pesee of es=4eeee. essere sees. s eemere erseeease es. se ese.d.e.es owns neewnas seemin see Siehed 84ae . r seevees seems desene. ames sa Ies Ace ene6mesed pop nemen se eeen solmee s y et emn are emesere eemeses et she fishin seesesse lesseesesenet omewhemene er theeoome. Adeseed a sell Desses er heart

. . ~ =~ e. - -

tiemeteneets teanses 4 940-38e8 4

t.,0 36, es0Jeet, -..t.-

88weeer Hose huweer Rees - 8ewmeer - Rene

• Noennee Rene 88vsumer Rose tmwee4 9eseen 723.079 $3 33'7.2 377J t t IPSA 100.623 = 07A tee.7st ess 47AM 21 3 mese, 400Act 343A 3elA06 tese teJe? 77.a 79277 67J 34Ase 32A femmes 323.277 393 4 171 A05 19ea 10eA3s 98.0 3eAte 27 7 12 Ass Ita 9mae Ste.391 361J 33SAe9 100.2 essee 16SA31 eSS eB.te0 44J 41A03 22.1 363 Ate 3904 letASS tes t MAse 70A tea 04 $6 8 30.604 32 9 femese 291.103 306.6 IMAos 162A el.791 100 5 3BA76 273 t t Aes 12.1

• 1 AN esher 99.907 Sees eta 13 147.1 teste 22A32 00 s 94A01 St2 SASS 21 A A 37.903 276 3 SeJtt 1782 10.757 FDJ 9eA73 7s.7 4Ase 328 Femees 22 Ate 21SS I7,902 117A

/ Reseae:

12.23S 82J 3AOB 38.3 1 Age 18.0 herweem 892Asa sees os.776

• 19e S 3eA23 e0I4 t?.ase as.t 7J3e $4A seerih Censres 304A4e Seveh 300.1 101.??? " 179 3 63Ast . et A 38.301 4SA 12A76 ft A

• 223.4 0 37s.2 194.747 ' tee 6 et.937 63A Weese 9 18.1 38.748 17A36 MA 104.tes 270 1 e0Att + IMS 39A02 MS 2OJet 62 9 9.ges MJ

, esoft?MSat?

4 8esa gastead 43AS4 tensae

• • 367.2 23308 & teSA to.047 e2.2 4Aes 38 4 1Ae8 SSA .

4.134 306 4 2.169 t 302 7 1A38 eFA des 464 fase Messoshes 230 30 4

' 2.708 339 e 1 A42 f 1874 See 83.2 372 39 2 Weasione 1 63 tea tAS3 3e7J 009 = 170A 300 73 5 22t 48A 92 SSJ hosessehweetts 21.277 308 3 f t Al2 e 197.1, 4.748 31.7 2.963 37J 082 14A Rhose $eene 3Ag7 41$ $ 2,t t e

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e. 227.7 748 M5 388 33 8 tes 96 6 30A30 SA23

• tesa 2.481 79 8 tAes te.4ee Ass mense 32.1 del 14J 8ee= Vest 148.408 ( 322.1 308 1 74Ae9 y 300 e , 29.775 79 4 12280' 38 8 SA33 14A 7tAse

• 383.1 36J79 e 201J . 93 ASP 75 0 S.78 SL7 2.310 12e

'es= Jeresy 4 3789

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• 7tA02 che t aus + tus MAes eFA 17A33 43e sJes 30 2 e 37J29 398 3 19.302 t eOS 9A17 08.1 4 Jet 39A S At f 973 ladeae 6. 17.777

• 338.3 9 036 S,422 Itause.e 970 4 102J 2Aes eaJ 1.33 23A 43,247 3ss.1 30.516 102.7 9A30 adesasse ell 433e 43.1 2.100 194 39.273 3 21.9 14A03 1634 7.365 to t 3.see 42A W.econsen 1 Ae2 21 e 16.173 3003 7 Ate t ?OA 4.199 SO S S Age 43.3 set 30.5

• host 8 earth Central 80 Ate 357A hemaseste 30.189  % t ?S A 17 Ass I0t a S.73e 62D 4.230 2SA 12.203 307A 0.399 tet A 3Ast 92 8 IADe taan 10349 469 336 30A 378 9 S.523 192.4 3.190 108.4 I Asl 42.1 he'uowe SOS 38 2 t e.42e 3st 7 9.349 t el.? 8.182 1973 2A23 North Dohete 2A73 327 4 990 62 8 1.343 MS Seeth Dekete 1924 900 90 2 age etJ 203 31 4

), 2A16 306 3 1.243 181 3 721 106.9 est et.7 8ertreehe S.465 23e 34.7 Keases 353.2 2A39 tees 1 AOS 1034 700 St.1 act 2SJ e300 assa 4A38 9 74.7 2J18 98 4 f.287 95 3 Ste 24.7 80U7M 5eveh Atse ase Desseere -

193.178 2A17 330 4 SO 493 $ 1780 alA00 01 2 97Ae7 30 3 eAte 23.7 346 4 sit 198 3 339 58.2 232 39 2 edervtead 12.963 3064 7.230 IN 22 4 174 3 2ADJ Bee las7 372 70s 17A Deeeert et Ceaunas.e 2249 330 4 8.54e 220.7 942 77J 3M ela 34 12A www.a e 14313 3es 4 7All 150.1 3 DSS 798 2.43 40 3 1Aet

• Weses Wetiase 7Al2 30.7 431 2 3 4e9 1s0.5 1.?st 973 1Ae4 87A herm Cereswie 16 Ate 402 27A 307 3 e.255 190 3 SA32 e2A S7J Seeth Coresme 8.397 304 4 3A57 3.135 f. ass ses Georges 138 S 2.731 MS 1A22 SFS See 38 4 14A35 3s33 7.103 1423 5.280 106 4 2JS7 Florese SSA 1.29s 38.9 23Ast 389.7 19.4Ce 230.S SAes 108 5 3Ae3 47J Emet amush Contrer 49A96 1 A27 22D Keaevsky 334 2 22At t J- 867A 15A62 113.2 SA34 58.7 3As7 SeJ 7eaneseos 12AA0 354.1 8301 ' 172 1 3A70 104.1 9A80 98 4 MB 25 4 14A06 341 9 7.202 170 9 4A40 194 3 l Aashame 2.2 70 M.1 1.144 27 4

' S t ADS 302.7 BAa4 163J 4250 199 2 2Jt3 63 9 thee'enced 7A74 1.127 30 8 33SD 3.724 198 2 2.793 tieA t.402 43 4 l West leum Control 000 29.3

, 64.390 303.7 34A43 182 4 19AFS 92A t t A90 arteaese - 7.797 300.7 2J39 I 94 3 Sale 30 6 toweeae 188 3 2.55e 12tJ 1.23 Se e See asA 12514 220 4 0.439 1876 3.425 89 2 Oaieneme SASG 359 9 S.102 2.302 Se e tes "28.7 Tesee 184.4 3A00 106 9 1AM et.1 e71 at S 34A22 272 4 18A53 'St A 10A01 SSS SA2e St.S 3.201 254

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23Act 233 3 13 Ale -f-132 4 4 Joe S3A SAse 81.7 teentea. 2,1 ge 2g03 1,131 3 Ass StA teene 196 2 642 e53 991 70 9 22 3e3 2.107 3s32 t.9 73 94tj s87 32 7 te7 08.2 ges

1. ve**4 1.107 3e38 493 32 0 Caserees 136 4~ 254 es t 351 904 tes 90 2 8ese nsense

. G.127 237.2 3.it3 12tf1 1SSS 80 2 3 Joe 53 8 87 24 4 1 Age 1 71.s 1.430 122.4 013 A*.sene 32A tes 78 4 S38 493 S.401 2373 3.4e4 1523 1se00 st1 van 2.6,9 90 4 703 lA h*=ede

-1 1231 too ese 94A SJ.a57S MS Me a,o 1 A 74 Pet A 912 140.7 420 se t 3 71 00 8 185

• • c4 - 30 3 teseheyles . et.tes 3829 47401 t 163 A 23JS4 et t o.323 4eJ sat 3 22.7 10A90 301.7 4.1 21 y 169 5 3 ADS el.? lA44 St.1 O eeen see 23.S 7.293 313.1 3394 171 A 2.261 98.7 IJ01 Me Cas4 erne Gl.218 20e l 35.700

$30 27J essene _ 16S e 17.See ets teas 3 40 s 4. Pee 22.1 30g gs 237 - gg e 30 M*=e's -

• 173 433 li3 t 1;g 3tA l A31 tetJ 953 1074 381 434 3e3 3'. ar 143 to t h b

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AFFIDAVIT OF ELIZABETH B. ENTWISLE I, Elizabeth B. Entwisle, being duly sworn, do sta te:

1. Tha t Intervenor CNRS 's Second Supplementary Response to Licensee 's First Set of Interroga tories was prepared under my directio'n and supervision.

2. That the responses contained therein are true to the best of my knowledge, informa tion and belief.

M . b Elitsbeth B. Entwisle SUBSCRIBED AND SWORN to before me this Y day of October, 1982.

A X-4 h LG t?U A ypygt;g PITTSSUROH, ALLEGHENY COUNTY EY CONulS$10N EXPIRES July 23,iggg Nm6er, Penntyivania Association of N% ,

o G

i i

I i

d UNITED STATES OF AMERICA NUCLEAR REGULATP.Y COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

) Docket No. 50-170 ARMED FORCES RADIOBIOLOGY )

RESEARCH INSTITUTE )

) (Application to Renew (TRIGA-Type Reactor) ) Facility License No. R-84)

CERTIFICATE OF SERVICE I hereby certify that copies of Intervenor CNRS' Second Supplemental Response to Licensee's First Set of Interrogatories (and exhibits thereto) . have been served on the following persons by deposit in the United States mail, first class, this gth day of. October, 1982:

, Cq(w{A _ .-- --

! Robett L.. Brittigan, Esq. *

. General Counsel I Defense N'uclear Agency J

• Washington, D.C.. 20305 Richard Bachmann, Esq.

t Counsel for NRC Staff U.S. Nuclear Regulatory Commission Washington,. D.C.. 20555 .

1 l

Helen.Hoyt,.Esq., Chair Administrative- Judge Atomic. Safety and. Licensing

Board Panel l

U.S. Nuclear Regulatory Commission.

Washington, D.C. '20555 .

k' Mr. Ernest E. Hill Administrative J.udge .

Lawrence.Livermera Laboratory -

University of' California-P.O.. Box 808, L-123 Livermore, California 94550 .

.