ML20042A159

Response to NRDC 820305 Revised Statement of Contentions & Bases.Addresses Position Re Admissibility of Each Contention & Discovery on Each Contention.Certificate of Svc Encl

ML20042A159
Person / Time
Site:	Clinch River
Issue date:	03/19/1982
From:	Bergholz W, Edgar G ENERGY, DEPT. OF, PROJECT MANAGEMENT CORP.
To:	NRC COMMISSION (OCM)
References
NUDOCS 8203230156
Download: ML20042A159 (125)

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MAR 2 e 1992&

In the Matter of rad !J7pfm b UNITED STATES DEPARTMENT OF ENERGY )

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) ~ tG PROJECT MANAGEMENT CORFORATION )

) Docket No. 50-537 TENNESSEE VALLEY AUTHORITY )

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(Clinch River Breeder Reactor )

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APPLICANTS' RESPONSE TO NRDC'S REVISED STATEMENT OF CONTENTIONS AND BASES Pursuant to the Board's Prehearing Conference Order of February l i , 1982, the United States Department of Energy and Proj ect Management Corporation, acting for themselves and on .sehalf of the Tennessee Valley Authority (the Applicants' , hereby submit their response to NRDC's Revised Contentions and Bases, dated March 5, 1982. In what follows, the Applicants will address (1) their positions concerning the admissibility of each contention and (2) 1/

their positions as to discovery on those contentions.-

-1/ In order to place Intervenors' Revised Contentions in the proper context, the parties must remain mindful of the extensive procedural background of this proceed-ing. The Licensing process for the Clinch River Breeder Reactor began approximately seven years ago.

NRDC and the Sierra Club sought to intervene on July 15, 1975 and were granted permission to intervene on Continued 820323o156 820319 DR ADOCK 05000537 PDR hDf

1. NRDC'S REVISED CONTENTIONS Two general principles should govern the Board's consideration of NRDC's revised contentions. First, NRDC has an obligation to demonstrate that the non-timely filing of its contentions is supported by " good cauce". 10 C.F.R.

$ 2.714. In the context of the CRBRP, NRDC must demonstrate the existence of new information not available at the time it initially filed its contentions. Philadelphia Electric Cat. (Peach Bottom Atomic Power Station, Units 2 & 3), LBP 77-12, 5 NRC 486, 487 (1977); Cincinnati Gas and Electric l

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October 9, 1975. Subsequently, NRDC's Contentions were the subject of extensive pleadings and numerous rulings as to admissibility by the Board, Appeal Board, and Commission. During the period from Novenber 1975 to March 28, 1977, the parties to this proceeding engaged in extensive discovery. For its part, NRDC filed 21 sets of Interrogatories on the NRC Staff, 15 sets of Interrogatories on Applicants, 7 sets of Requests for Admissions and 4 Requests for the Production of Documents. NRDC's Interrogatories alone amounted to over 2400 questions. In addition, NRDC was provided thousands of pages of documents during discovery. By March 28, 1977, this proceeding had progressed to the point that: (1) the FES had been issued recommending the grant of a Construction Permit; (2) the Site Suit-ability Report had been issued which found that the Clinch River site is suitable from the standpoint of radiological health and safety; and (3) the Board had ordered hearings to commence on June 4,1977 and run in continuous session until completion. Thus, at the time this proceeding was suspended on April 25, 1977, NRDC had been given abundent opportunity, over a two-year period, to raise numerous contentions, obtain discovery on those contentions, and prepare its case for hearing.

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a Co. (William H. Zimmer Nuclear Station), LBP-79-22, 10 NRC 213 (1979).

Secondly, in addition to demonstrating good cause (i.e., new information), NRDC must also provide the bases for its revised and new contentions with reasonable specificity. 10 C.F.R. S 2.714(b) (1981). In Commonwealth Edison Co. (Byron Nuclear Power Station, Units 1 & 2), LBP 80-30, 12 NRC 683, 689 (1980), the Board succinctly stated the purpose of this requirement in the following terms:

It is incumbent upon intervenors to frame their contentions with sufficient preciseness to show that the issues raised are within the scope of recogniz-able issues to be considered in an adjudicatory proceeding.- To this end, a hearing participant 'must be specific as to the focus of the desired hearing,'

and contentions must serve the purpose of defining the ' concrete issues which are appropriate for adjudication in the proceeding.' Properly framed conten-tions will further reasonably inform the other parties what issues they will be required to defend against or oppose to develop a complete record in an evidentiary hearing.

See also Philadelphia Electric Co. (Peach Bottom Atomic l

l Power Station, Units 2 and 3), ALAB-216, 8 AEC 13, 20 l

(1974). Contentions which are vague, open-ended and l

conclusory clearly do not meet this standard. Offshore Power Systems (Manufacturing License for Floating Nuclear Power Plants), LBP-77-48, 6 NRC 249 (1977); Kansas Gas and

! Electric Co. (Wolf Creek Generating Station, Unit No. 1),

ALAB-279,1 NRC 559, 574 (1975) . As a corollary, revised contentions which merely duplicate existing contentions are also improper. Offshore Power Systems, supra at 253; Metropolitan Edison Co. (Three Mile Island Nuclear Station, Unit 1), LBP-80-5, 11 NRC 136 (1980) .

As demonstrated below in submitting its revised contentions, NRDC has raised a number of new issues which are not supported by any new information developed since the suspension of proceedings. In addition, many of NRDC's con-tentions are vague and conclusory and fail to meet the requisite standard of specificity. Finally, certain of NRDC's contentions duplicate matters raised by existing. con-tentions and serve only to add uncertainty and confusion as to the matters which are properly at issue. With these governing principles in view, the Applicants will proceed to 2/

address the pertinent provisions of each NRDC contention.-

-2/ As noted in Applicants' Status Report filed on March 10, 1982, in stating no objection to Intervenors Revised Contentions, Applicants reserve and do not waive those arguments previously advanced in connection with the admission of all previous contentions. Appli-cants concur in the withdrawal of Contentions 1(a) and

15. Applicants do not have additional objections to the admissibility of Contentions 5, 8(a), (b), (c), and 9, subj ect however, to the qualifications set forth in the Board's Order of April 6, 1976 admitting these con-tentions. Further, Applicants do not have additional objections to the admissibility of Contention 8d(2),

> subject to the qualifications set forth in the Board's Order of April 27, 1976. As to Contentions 2, 3, 4, 18, 19, 21, and 23, in addition to the foregoing, Applicants reserve the right to argue that the matters Continued

CONTENTIONS 3(d) and 3(h)

(d) Neither Applicants nor Staff have demonstrated that the design of the containment is adequate to reduce calculated offsite doses to an acceptable level.

(h) Since neither Applicants nor Staff have estab-lished that the models, computer codes, input data and assumptions are adequately documented, veri-fled and validated, they have also been unable to establish the energetics of a CDA and thus have also not established the adequacy of the contain-ment [or] of the source term for post accident radiological analysis.

OBJECTION:

To the extent that Contention 3(d) addresses the adequacy of the " design of the containment ... to reduce calculated offsite doses to an acceptable level", and Contention 3(h) takes issue with the " adequacy of the containment for post accident radiological analysis",

Contention 3(d) is palpably duplicative, and should not be admitted. See Metropolitan Edison Co. (Three Mile Island Nuclear Station, Unit 1), LBP-79-34, 10 NRC 828, 838 (1979). If NRDC should argue that it is not duplicative, then it must necessarily contain a " hidden agenda" which Applicants cannot discern, and which Applicants cannot hope to meaningfully address in testimony. As the Appeal Board stated in Wolf Creek, supra at 576:

raised in these contentions need not be litigated prior to the issuance of an LWA.

The Applicant is entitled to a fair chance to defend. It is therefore entitled to be told at the outset with clarity and precision, what arguments are being advanced and what relief is being asked. . . . So is the Board below. It should not be necessary to speculate about what a pleading is supposed to mean.

Accordingly, Contention 3(d) should not be admitted.

CONTENTION 3(e)

As set forth in Contention 8(d) neither .

Applicants nor Staff have adequately calcu:ated the guideline values for radiation doses from postulated CRBRP releases.

OBJECTION:

By its very terms, Contention 3(e) does no more than duplicate Contention 8(d). Both Contention 3(e) and 8(d) concern guideline values for radiation doses from postulated CRBRP releases. There obviously is no need for redundant contentions and Contention 3(e) should, therefore, be rejected. See Metropolitan Edison Co., supra at 142; Offshore Power Systems, supra at 253.

To the extent that Contentio- 3(e) raises new unstated issues not encompassed within Contention 8(d), it lacks the required specificity and basis and should be rej ected . Applicants should not be required to guess at the intended scope of Contention 3(e), when by its terms Intervenors claim that it merely duplicates Contention 8(d) .

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CONTENTION 4(d) i Neither Applicants nor Staff have given sufficient attention to CRBR accidents other than the DBAs for the following reasons:

(d) Neither Applicants nor Staff have adecuately identified and analyzed the ways in which human error can initiate, exacerbate, or interfere with the mitigation of CRBK accidents.

OBJECTION:

In Contention 4(d), NRDC makes the vague and unbounded contention that Applicants have not adequately analyzed " human error" in the context of accidents. No attempt, however, is made to identify the type of " human error" with which NRDC is concerned. In Metropolitan Edison Co., supra, a similar contention was rejected by the Board as lacking in specificity and basis. There, an intervenor submitted a contention that the analysis of safety systems must demonstrate that the systems could withstand accidents 1

l ehat " reflect all conceivable combinations of human and l mechanical failure." The Board rejected the contention i

noting that it was " vague" and " unbounded" and therefore inadmissible. Similarly in this case, the term " human error", like the phrase "all conceivable combinations of human and mechanical failure," fails to provide any notice to Applicants, Staff, or the Board as to the specific nature of NRDC's concerns.

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NRDC's statement of bases for this contention is similarly of no assistance in defining the scope of the term

" human error." The bases submitted by NRDC are nothing more than a listing of information derived from the incident at Three Mile Island. NRDC fails to establish which portions of this information define its concerns with CRBRP. In short, no attempt is made to establish a " nexus" between this information and the CRBR licensing proceeding. See Consumers Power Co. (Big Rock Point Nuclear Plant), LBP 4, 11 NRC 117 (1980) . As the Board stated in Offshore Power System, supra, "[i]n an adversary proceeding, a party must do its own homework ..." and "there is no duty which .

requires the Staff to plow through various publications cited by an intervening party in order to determine the factual basis- if any, for a conclusional contention."

Absent such a nexus or factual basis, the contention is meaningless and should be rejected.

CONTENTION 6 Neither Applicants nor Staff have established that the site selected for the CRBR provides adequate protection for public health and safety, the environment, national security, and national energy supplies; and an alternative site would be preferable.

OBJECTION:

In its original contention admitted by the Board on April 6, 1976, NRDC specifically limited this contention to the factors enumerated in the subsequent subparts by the insertion of the phrase "for the following reasons." NRDC's revised Contention 6, however, omits the qualifying phrase and thereby impermissably broadens the scope of Contention

6. See Metropolitan Edison Co. (Three Mile Island Nuclear Station, Unit 1) LBP-79-34, 10 NRC 829 836 (1979) (conten-tions which go from the specific to the general are impro-per). As presently revised, the proposed contention is unduly vague and conclusory in violation cf the specificity requirement of 10 C.F.R. S 2.714 (1981). Indeed, as rewrit-ten, Contention 6 permits NRDC to introduce information regarding unstated issues without providing Applicants any notice of the issues they will be required to defend against or oppose. Philadelphia Electric Co., supra at 20. As a matter of fundamental fairness, NRDC should be required to set forth all of the bases upon which this contention is founded. NRDC can hardly complain that it is required to inform Applicants of all of the grounds for its c- c ,-

tion. Accordingly, Contention 6 should be limitec _v the l

formulation originally admitted; i.e., subject to the 3 '/

limiting phrase "for the following reasons".-

CONTENTION 6(b)

The site meteorology and population density are less favorable than most sites used for LWRs.

(1 ) The wind speed and inversion conditions at the Clinch River site are less favorable than most sites used for light-water reactors.

(2) The population density of the CRBR site is less favorable than that of several alternative sites.

(3) Alternative sites with more favorable meteorology and population characteristics have not been adequately identified and analyzed by Applicants and Staff. The analysis of alternative sites in the ER and the Staff Site Suitability Report gave insufficient weight to the meteorological and population disadvantages of the Clinch River site and did not attempt to identify a site or sites with more favorable characteristics.

OBJECTION:

NRDC has revised Contention 6(b) to include references to " population density," " population characteristics" and " population disadvantages". NRDC's statement of basis indicates that "several references have been included to reflect the need for analyses of population densities at the CRBRP site and alternate sites." NRDC

-3/ In its revised Contention 4, NRDC included the qualifying phrm se "for the following reasons" just as it had includeo : hat phrase in its original contention. Ne reason is advanced by NRDC for omitting this phrase frse Contention 6.

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4 Revised Contentions at 29. / Further, NRDC states that "the basis for this addition is new information relating to the appropriateness of remote siting" (NRDC Revised Contentions at 29), such as:

(1 ) The Office of Nuclear Reactor Regulation, NRC, Report of the Siting Policy Task Force (NUREG-0625) (August 1979) which recommends changes in NRC siting policy, but does not itself establish any policy; (3) Proposed rule regarding the review of alternative sites under NEPA (45 Fed. Reg. 24168, April 9, 1980);

(4) Notice of Intent co prepare an Environmental Impact Statement for Revision of the Regulations Coverning the Siting of Nuclear Power Plants (45 Fed. Reg. 79820, December 6, 1980); and (5) NRC, A Comparison of Site Evaluation Methods (NUREG/CR-1684) (July 1981).

In a footnote to the foregoing list of alleged new information, NRDC correctly states that these items of information " arose from the requirements of the NRC 1980 Authorization Act, Pub. L. No.96-285, 94 Stat. 780 (June 30, 1980. ..." NRDC, however, conveniently ignores the fact that Section 108 of the 1980 Authorization Act, whLch directs the NRC to establish demographic requirements for siting, exempts any facility from this requirement for which

--4/ Revised Statement of Contentions and Bases of Intervenors Natural Resources Defense Council, Inc. and The Sierra Club at 30, note 2 (hereinafter "NRDC Revised Contentions").

an application for a construction permit was filed before October 1, 1979. Section 108(b) states:

(b) The regulations promulgated pursuant to this section shall provide that no construction permit may be issued for a utilization facility to which this section applies after the date of such promulgation unless the facility complies with the requirements set forth in such regulations, except that regulations promulgated under this section shall not apply to any facility for which an application for a construction permit was filed on or before October 1, 1979.

Similarly, the notice of proposed rulemaking, which is specifically relied upon by NRDC as item 2 of its "new information", states:

i This rulemaking is intended for applica-tion to facilities for which an applica-i tion for a construction permit is filed

! after October 1, 1979. This is in

! accordance with Section 108 of the 1980 NRC Authorization Bill.

45 Fed. Reg. 50350.

Because the CRBRP application for a construction permit was filed in 1975, both the Act and the proposed rules are inapplicable to the CRBRP. Thus, contrary to NRDC's implicit representation, there is no new statutory or regulatory requirement applicable to this proceeding to consider population density or population characteristics in 5/

the manner suggested by NRDC.- To the contrary, by 5f Philadelphia Electric Co., supra at 487.

"grandfathering" all proceedings in which an application for a construction permit had been filed before the cifective date of Section 108, both the Congress and the NRC expressly 6/

excluded consideration of those issues in this prcceeding.-

CONTENTION 6(c)

Since the gaseous diffusion plant ... the Y-12 plant ... are in close proximity to the site an accident at CRBR could result in the long term evacuation of those facilities. ...

OBJECTION:

NRDC has revised Contention 6(c) to include a reference to the Y-12 plant. NRDC alleges that the basis for the addition of Y-12 to Contention 6(c) is "new 7/

information derived from the Progressive case- concerning

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national security activities at the Y-12 plant"I- The Progressive decision, supra, is silent as to any information

-6/ In addition, revised Contention 6(b) should be rejected for the further reason that it lacks the requisite specificity. NRDC claims to base inclusion of demo-graphic consideratio s on "new information relating to the appropriateness of remote siting", but nowhere is NRDC's suggested definition for the term " remote siting" provided by NRDC or by the sources it citas.

Consequently, the contention fails to reasonably inform Applicants of the specific '.ssue Applicants will be-required to defend against er oppose. See Commonwealth Edison Co. (Byron Nuclear Power StationT Units 1 & 2),

LBP-80-30, 12 NRC 683, 689 (1980).

-7/ U.S. v. Progressive, Inc. 467 F. Supp. 990 (W.D. Wis.

1979), appeal dismissed, 610 F.2d 819 (7th Cir. 1979).

8f NRDC Revised Contentions at 30.

concerning Y-12. Moreover, the only fact which NRDC would have needed in order to file this contention prior to 1977 is that Y-12 is a national security facility. The Y-12 facility has been in existence since well before the CRBRP application was filed, and it is well known that Y-12 is a national security facility supporting nuclear weapons product *.on. This information had been in the public domain for at least a decade before the NRDC began filing is contentions in this proceeding. Appendix A contains some r ipresentative public documents concerning Y-12 which were published prior to 1977. NRDC thus had adequate notice that Y-12 was a national security facility, and it had ample, opportunity to raise this contention prior to 1977.

Notwithstanding NRDC's claim of new information, the essential facts that might serve as a basis for inclusion of Y-12 in this contention -- that Y-12 is a national security facility involved in the production of nuclear weapons --

are simply not new. NRDC has utterly failed to support its non-timely filing with good cause for late admission of Y-12 into Contention 6(c).

CONTENTION 8(d)

(d) Guideline values for permissible organ doses used by Applicants and Staff hcVe not been shown to have a valid basis.

(1) The approach utilized by Applicants and Staff in establishing once-in-a-lifetime organ dose equivalent limits corresponding to a whole

body dose of 25 rems is inappropriate because it fails to consider important organs, e.g.,

the liver, and because it fails to consider new knowledge, e.g., recommendations of the ICRP in Reports 26 and 30.

OBJECTION:

In revising Contention 8, Intervenors have included in subpart (d) issues which previously were included in Contention 7. The original Contention 7 specifically alleged that the guideline values for bone and lung exposures in the PSAR had not been shown to have a valid basis. As rewritten, however, the contention is no longer limited to bone and lung exposures. Instead, Intervenors have made the contention vague and conclusory by contending that "important organs" were not considered without specifying which important organs were not con-sidered. If this Contention seeks to challenge the thyroid and whole body values set forth in 10 C.F.R. S 100.11 (a) ,

footnote 2, it is an impermissible challenge to the

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Commission's regulations.- Similarly, in Contention 8(d),

Intervenors claim that Applicants did not consider "new knowledge" again without specifying the "new knowledge which was not' considered." Intervenors have an obligation to provide Applicants with the bases of their contention with 9f See footnote 17, pp. 29-30 infra.

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reasonable specificity. Commonwealth Ediscn Co., supra at 689. In revising Contention 8(d), Intervenors must have had in mind the specific "new knowledge" which allegedly was not considered by Applicants and Staff. Intervenors should be required to specify precisely which new knowledge was not considered. Applicants have no objection to the contention provided that the example given in the contention is a limitation on the scope of "new knowledge". Metropolitan Edison Co., supra at 836. Accordingly, the contention should be admitted only in the following form:

8(d)(1) The approach utilized by ,

Applicants and Staff in establishing once-in-a-lifetime organ doses for lung and bone in equivalent units corresponding to a whole body dose of 25 rems is inappropriate because it fails to consider the recommendations of the ICRP in Reports 26 and 30.

CONTENTION 14(c)

(c) Applicants and Staff must systematically analyze all neutron activation products that may be produced in the proposed CRBR to determine the potential isolation period, following decommis-sioning, and then provide a comprehensive analysis of the costs (both economic and societal) of decommissioning. Neither Applicants nor Staff have adequately analyzed the implications of neutron activation products, such as nickel-59 and niobium-94, for the decommissioning of the CRBR.

OBJECTION:

Applicants have no objection to this contention provided the examples given in the second sentence of

Contention 14(c) (i.e., nickel-59 and niobium-94) are limitations on the scope of the phrase " neutron activation products." Metropolitan Edison Co., supra at 836. In this regard, it should be noted that Intervenors' original Contention 14(c) limited the contention to the analysis of nickel-59. In revising the contention, Intervenors claim new information suggests that niobium-94 should also be considered in the decommissioning analysis. If Intervenors are aware of other " neutron activation products" which should be considered, they should be required to inform Applicants in order to permit Applicants to prepare their case. Accordingly, since the two examples are the only neutron activation products which Intervenors now believe were not adequately considered, their contention should be admitted only as follows:

(c) Applicants and Staff must systematically analyze all neutron activation products that may be produced in the proposed CRBR to determine the potential isolation period, following decom-missioning, and then provide a comprehensive analysis of the costs (both economic and societal) of decommissioning. Neither Applicants nor Staff have adequately analyzed the implications of nickel-59 and niobium-94 for the decommissioning of the CRBR.

l l CONTENTION 16 Applicants and Staff have given inadequate attention to the presence of liquid radioactive effluent from the Oak Ridge Reservation and the radioactive sediment already present in the Clinch River.

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(a) In assessing alternative sites for the LMFBR demonstration plant, the suitability of the CRBR site, and the NEPA cost / benefit analysis, neither A 7 plicants nor Staff have adequately considered t.ne increased risk of radiation exposure to existing radioactive sediment, through dredging, pumping and river traffic, that would occur at the Clinch River site.

(b) In assessing alternative sites for the LMFBR demonstration plant, the suitability of the CRBR site, and the NEPA cost / benefit analysis, neither A7plicants nor Staff have adequately considered tie health and safety effects of CRBR operations and discharges in conjunction with the cumulative effects of nearby existing and proposed plants, including the ORNL, the Oak Ridge Gaseous Diffusion Plant, the TSA synfuels plant, and the PCB low-level radioactive waste incinerator.

(c) The Staff baseline monitoring program is inadequate because neither Applicants nor Staff have an adequate understanding of existing radioactive contamination of the Clinch River, and therefore cannot adequately insure that CRT;R radioactive releases to Clinch River will meet the requirements of 10 C.F.R. Part 20.

(d) Applicants' proposal to transport components and materials for the CRBR by barge rather than rail would increase the risk of radiation exposure from radioactivity existing in the Clinch River sediment. It is therefore in violation of the 10 C.F.R. Part 20 requirement that Applicants maintain radioactive levels in effluents to unrestricted areas as low as is reasonably achievable.

OBJECTION:

At page 32-33 of its revised contention pleading, NRDC states its basis for filing this new contention as follows:

l This is a new contention based upon new information indicating that Clinch River sediment radioactivity levels may be highe?c than those

indicated in Applicants' Environmental Report.

The December 1981 Environmental Impact Report of the Tennessee Synfuels Association (TSA) on its proposed Oak Ridge, Tennessee synfuels plant indicates that TSA is presently sampling Clinch River radioactivity levels near the CRBR site at points one-half mile apart. The sabpling referred to in Applicants' ER (Fig. 2.8-6), however, was performed at points approximately one mile apart. TSA's failure to rely upon Applicants data, as well as the discrepancy in sampling techniques, triggered Intervenors' review of earlier scientific documents and ongoing research regarding Clinch River radioactivity levels.

These documents and research indicate that Applicants' ER and the FES are deficient since they do not adequately discuss the radioactivity levels, liquid effluent and radioactive sediment in the Clinch River. See Clinch River Study (Struxness 1967); USGS, AEC, ORNL study (Pickering 1969); unpublished core sample data collected in 1977-1980 analyzed by ORNL; and environmental monitoring report data from the Oak Ridge Gaseous Diffusion Plant (Union Carbide Nuclear Division 1980). (Emphasis added.)

The Applicants submit that:

(a) the Applicants' 1976 Environmental Report (ER) fully discussed radioactivity in the Clinch River sediments (a copy of relevant pages is attached hereto as Appendix i

B). The Struxness 1967 and Pickering 1969 studies cited by l

NRDC were referenced and discussed in the 1976 ER. See Appendix B, page 2.6-8 and footnotes 12, 13.

(b) the TSA report does not provide any significant new information concerning radioactivity in the Clinch River sediments (a copy of relevant pages is attached hereto as Appendix C). The TSA relies upon the Struxness 1967 and Pickering 1969 studies just as the Applicants'

ER. More importantly, in regard to radioactivity, the TSA concludes:

Review of the data from these above studies suggest that concentrations of the radioisotopes studied in the Clinch River sediments are at a very low level; that the distribution of the isotopes appears stable with time; and that the risk to humans from these sources appears to be very low.

The planned dredging operations, related to site preparation and to facility construction, will result in movement of certain quantities of the sediments. The combination of low contamination levels and apparent immobility of the containments suggest a low risk situation. 10/

(c) NRDC's statement as to the " apparent discrepancy" between the CRBRP and TSA sampling techniques is simply incorrect. NRDC states that the TSA contemplates sampling at one-half mile intervals, while CRBRP will sample at one mile intervals (acting Fig. 2.8-6 of the ER). In fact, the CRBRP will sample at approximately one-quarter mile intervals (see ER, Figures 2.8-11 and 2.8-12). More importantly, the TSA states that:

The samplings are being performed in the exact same manner as that used in the 1967 and 1977 studies mentioned above. Results should, therefore, be directly comparable to those studies' results. The proposed program will be reviewed by both the U.S. DOE and ORNL. (TSA at 5-43.)

10/ Appendix B, page 5-43. The Applicants' updated ER, Section 2.8, which includes all available data, reaches l a similar conclusion and confirms that conditions have not significantly changed since 1976.

On the basis of the foregoing, it is transparently obvious that the 1976 ER fully considered radioactivity in the Clinch River sediments, that nothing has changed since that time, and most importantly, that there is no new information available to justify admission of this new contention. NRDC has simply failed to state an acceptable 11 basis for admission of Contention 16.- /

CONTENTION 17 Neither Applicants nor Staff have demonstrated that sufficient fuel would be available for CRBR operation to enable the CRBR to demonstrate the objectives of the LMFBR program and remain in operation for a sufficient length of time to justify the project.

(a) According to DOE policy, the need for plutonium for the U.S. nuclear weapons program must take precedence over the need for plutonium for the LMFBR program.

(b) The U.S. weapons program is currently depleting existing DOE stocks of fuel-grade plutonium, the traditional source of plutonium for the LMFBR program.

(c) Neither Applicants nor Staff have demonstrated that alternative sources of fuel for the CRBR will-be available when needed for CRBR operation.

OBJECTION:

Intervenors, in questioning whether there is enough fuel for the Project are challenging the need for the 11/ Likewise, NRDC has uade no showing to justify the admission of a late-filed contention. See 10 C.F.R.

S 2.714(a)(1) .

Proj ect . This is a programmatic (planning) issue which is outside the permissible scope of this proceeding. The question of the availablilicy of fuel for the CRBR is a matter relating only to DOE's LMFBR and national defense programs and must be taken as given in accordance with the Commission's 1976 decision limiting the Board's review of DOE's (previously ERDA) programmatic planning decisions.

United States Energy Research and Development Administration (Clinch River Breeder Reactor Plant), CLI-76-13, 4 NRC 67 (1976). In that decision, the Commission clearly defined .

the scope of its review in the following terms:

Where, as in this'YAse, NRC licensing of a demonstration breeder reactor is mandated, deference to this basic objective of the Act -separation of responsibilities -- compels a careful delineation of our role so as to avoid undue interference with [ DOE's] overall planning functions. If nothing else, the Act makes clear that we must not decide the present issue so as to put the Nuclear Regulatory Commission in the position of scrutinizing afresh the judgments on long range energy research and development issues made by the agency to which such judgments were primarily confided.

l The Commission concluded that "its licensing process must be tailored in this case to avoid the Commission's substituting its judgment for that of [ DOE] with respect to the broad planning issues embodied in the LMFBR statement. ...

Conversely, matters of greater specificity, such as selection of the Clinch River site and reactor design

involve implementation of planning decisions." United States Energy Research and Development Administration, supra at 83-84.

The question of fuel availability is a " planning function" unrelated to " selection of the C1_nch River site and reactor design" and is entrusted solely to the Depart-ment of Energy. Just as the Board may not review the need for a demonstration breeder reactor, it may not review the availability of plutonium for that facility. Indeed, the question of fuel availability is itself fundamental to the determination of the need for the demonstration reactor and thus is plainly outside the p,urview of this proceeding.

CONTENTION 18 Neither Applicants nor Staff have demonstrated that Applicants' quality assurance program, to be applied to the design, fabrication, construction, and testing of the structures, systems, and components of th; facility, is 12/ It seems somewhat incongruous that NRDC would raise this issue in these proceedings when it has taken a position in direct conflict in another forum. In a recent letter to " Science" magazine (Reprinted in the March 12, 1982 issue), NRDC prote'sted the expansion of facilities for the production of plutonium, stating:

We suggest that the input from our existing production reactors at Hanford and Savannah River and the nuclear material recovered annually from weapons retired out of our burgeoning stockpile of 26,000 nuclear weapons are sufficient for the plutonium and tritium needs of weapons planners and designers for several decades to come.

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1 adequate to meet NRC requirements, or that s.ch program would protect the public health and safety adequately even if 1t complies with NRC requirements.

(a) Neither Applicants nor Staff have adequately demonstrated that the proposed quality assurance program will meet the requirements of General Design Criterion 1, 10 C.F.R. Part 50, Appendix A.

(b) Neither Applicants nor Staff have adequately described the proposed quality assurance program nor demonstrated how the applicable requirements of Appendix B wifI Fe satisfied, as required by 10 C.F.R. S 50.34(a)(7).

OBJECTION:

This contention is clearly untimely. The requirements and standards for a quality assurance program were in. existence in their present form at the time NRDC submitted its original contentions in July, 1975. See 10 C.F.R. S 50.34(a)(7), 10 C.F.R. Part 50, Appendix B. Both Appendix B and Section 50.34(a)(7) were promulgated on June 27, 1970. They provided NRDC sufficient notice at that time to challenge Applicants' quality assurance program. It is patently unfair to permit NRDC to raise this contention nearly eight years later.

NRDC seeks to justify this tardy contention on the "recently encountered difficulties" related to the NRC's quality assurance program discussed during Congressional testimony and in the NRC's 1980 Annual Report. NRDC would have this Board believe that this testimony creates a new need for review of the CRBR quality assurance program. To l

the contrary, neither the Congressional testimony nor the Annual Report raise any new issue or impose any new require-ment with respect to the CRBR quality assurance program that did not exist in 1975 when NRDC filed its original conten-tions. The applicable regulations have not been changed and there has been no indication of any inadequacy of the CRBR quality assurance program. Consequently, NRDC cannot justify the untimely submittal of this contention.

In addition to being untimely, Contention 18 is unduly vague. NRDC claims in Contention 18(a) and (b) that Applicants have inadequately demonstrated compliance with the requirement of Criterion 1,10 C.F.R. Part 50, Appendix A, have inadequately described the quality assurance program, and have inadequately demonstrated how the quality assurance program will comply with the requirements of Appendix B. In all these claims, however, NRDC identifies no specific inadequacies nor any indication whatsoever of how the CRBR quality assurance program is inadequate.

Absent a specific statement as to the alleged inadequacies, the Contention is vague, conclusional and improper and must be rej ected. See Commonwealth Edison Co. (Byron Nuclear Power Station, Units 1 & 2), LBP-80-30, 12 NRC 683, 689 (10S0); Wolf Creek, supra at 574-576.

l CONTENTION 19 Neither Applicants nor Staff have demonstrated that Applicants' plans for coping with emergencies are adequate to meet NRC requirements, or that such plans would protect the public health and safety adequately even if they comply with NRC requirements.

(a) The PSAR contains insufficient information regarding Applicants' ability to identify the seriousness and potential scope of radiological consequences of emergency situations within and outside the site boundary, including capabilities for dose projection using real-time meterological information and for dispatch of radiological monitoring teams within the Emergency Planning '

Zones.

(b) Applicants and. Staff have failed to account properly for local emergency response needs and capabilities in establishing boundaries for the plume exposure pathway and ingestion pathway EPZs for the CRBR.

(c) The PSAR contains insufficient analysis of the time required to evacuate various sectors and

distances within the plume exposure pathway EPZ for transient and permanent populations, nor does it note ' major impedicents to the evacuation or taking of protective actions.

(d) The PSAR contains insufficient information to l ensure the compatibility of proposed emergency l plans for both onsite areas and the EPZs, with facility design features, site layout, and site location.

(e) The PSAR contains insufficient information concerning the procedures by which protective actions will be carried out, including authorization, notification, and instruction

procedures for evacuations.

1 (f) Applicants' proposed emergency plans fail to take into account the special measures necessary to cope with a CDA, including the need for increased protective, evacuation and monitoring measures, reduced response time and special protective action levels.

(g) Applicants and Staff have failed.to provide adequate assurance that the proposed emergency plans will meet the requirements and standards of 10 C.F.R. S 50.47(b).

OBJECTION:

In proposed Contention 19, NRDC asserts that Applicants have failed to demonstrate that Applicants' emergency plans meet NRC requirements. In addition, NRDC asserts a residual risk claim that such plans would not protect the public health and safety regardless of compliance with NRC requirements. NRDC justifies the late addition of this contention on the revision of the NRC's emergency planning regulations on August 19, 1980 (45 Fed.

Reg. 55402). Apparently NRDC would have the Board believe that the NRC only recently established requirements regarding emergency plans. In fact, Appendix E to Part 50, which contains the NRC's requirements for preliminary approval of emergency plans during the construction permit stage was promulgated in 1970. Under Appendix E as originally promulgated, an applicant for a construction per-mit was required to establish the feasibility of an emer-gency plan (given the facility design and location) based on seven criteria, including internal organization, arrange-ments with government agencies, measures to be taken onsite 13/ 35 Fed. Reg. 19568 (Dec. 24, 1970), amended 38 Fed.

Reg. 1272 (Jan. 11, 1973).

and offsite, and provisions for emergency treatment.

Thus, when NRDC filed its original contentions, in 1975, Appendix E gave NRDC sufficient notice to examine and, if justified, challenge Applicants' emergency planning. NRDC chose not to do so and nothing regarding CRBR emergency planning has changed to warrant admission of NRDC's late contention.

Contention 19 is objectionable in three additional respects. First, NRDC asserts that Applicants' have failed to demonstrate that the emergency plans for the CRBR "are adequate to meet NRC requirements." This contention is irrelevant to this construction permit proceeding. Under Appendix E,Section II, a construction permit applicant need not establish actual compliance with NRC emergency planning requirements, but only the feasibility of meeting NRC requirements given plant design and location. Because Contention 19 expressly challenges Applicants' compliance with NRC requirements that are not applicable to this proceeding, it is inadmissible.

Secondly, NRDC claims in Contention 19(b) that Applicants have failed to demonstrate that they have 1

14/ Id.

l 15/ 10 C.F.R. Part 50, App. E, S II.

1

1 accounted for local emergency response needs and capabil-ities in establishing boundaries for plume exposure pathway and ingestion pathway EPZs for the CRBR. This contention is irrelevant to this proceeding because Appendix E,Section II (A)-(G) does not require such a demonstration. NRDC cites no authority for such a requirement in the regulatione. Accordingly, this contention must be rejected as irrelevant because it is not based on applicable NRC requirements.

Finally, NRDC claims in 19(f) that Applicants' emergency plans fail to account for CDAs. As with Conten-tion 19(b), this contention is not based on applicable NRC requirements regarding the evaluation of emergency plans in construction permit proceedings. Part 50, Appendix E,Section II contains no requirement that a construction

! permit applicant describe special emergency measures for coping with a CDA. Accordingly, this contention must be

(

rejected because it attempts to go beyond applicable NRC i

regulations, and constitutes a challenge to those regulations.

lil Id-

17/ 10 C.F.R. 5 2.758. A federal appellate court has stated that, even if assumptions made by a regulatica might be incorrect

i the forum for challenging it was correctly held not to be the licensing Continued

CONTENTION 20 Neither Applicants nor staff have adequately described the risks and consequences associated with CRBR accidents beyond the design basis.

(a) The Staff concludes in the FES that CRBR accident risks can be made acceptably low with the incorporation of certain features and design requirements, yet neither Applicants nor Staff have adequately described these additional features and requirements, nor demonstrated that they will sufficiently lower the risks of CRBR accidents.

(b) NRC policy reflected in 45 Fed. Reg. 40101 (June 30, 1980), requires a discussion of consequences substantially greater in scope and detail than that contained in the FES.

OBJECTION:

In Contention 20, NRDC challenges the analysis of accidents contained in the Final Environmental Statement prepared in 1977. In particular, NRDC claims that the 1977 hearing but the rulemaking.

Union of Concerned Scientists v. AEC, 499 F.2d 1069, 1090 (D.C. Cir. 1974). See Vermont Yankee Nuclear Power Corp. , ALAB-179, 7 AEC 159,163-64 (1974); Long Island Lighting Co. (Shoreham), ALAB-99, 6 AEC 53, 55-56 (1973). Section 2.758 does contain an exception, if the intervenor can meet a heavy burden of showing special circumstances that would make the application of the regulation "not serve the purposes for which

[it] was adopted." Id. One court has emphasized the heavy burden, by noting that an " applicant for waiver faces a high hurdle even at the starting gate." WAIT Radio v. FCC (I), 418 F.2d 1153, 1157 (D.C. Cir.

1969). Upon remand, the FCC again refused to waive its rule, and was affirmed by the same court. WAIT Radio

v. FCC (II), 459 F.2d 1203, cert. denied, 409 U.S. 1207 (1972). See Duke Power Co. (Catawba Units 1 & 2), LBP-74-22, 7 700I 659, 686 (1974).

31 -

FES is inadequate in regard to accidents in two respects:

(a) the FES does not adequately describe the features and design requirements which will minimize accident risk; and (b) the FES does not adequately discuss the consequences of Class Nine accidents.

In submitting this "new" cot.tention, NRDC recognizes the obvious fact that contentions challenging the FES could have been (indeed, should have been) asserted five years ago. NRDC nonetheless argues that it may submit this untimely contention without any showing of new information or good cause because "it was Intervenor's position - never ruled upon by the Board - that the FES was inadequate and should have been recirculated prior to hearing." NRDC concludes from this that "it was not incumbent on Intervenors to amend this contention at that time, and an amendment now is appropriate."

! In making this argument, NRDC neglects to point out to the Board-the fact that its challenge to the FES had absolutely nothing to do with the accident analysis contained in Section 7 of the FES. Rather, in its earlier challenge, NRDC claimed that the FES was inadequate because i

l the FES contained a more elaborate discussion of alternative 18/ NRDC Revised Contentions at 36.

l 19/ Id.

I national sites than that contained in the DES. NRDC apparently would have the Board believe that, having filed a motion concerning one portion of the FES, NRDC was relieved of any responsibility to file contentions in a timely manner concerning any other portion of the FES. Not surprisingly, NRDC does not explain why it failed to file this additional contention regarding the analysis of risks and consequences 21/

of accidents contained in the DES.--

NRDC was given the opportunity to file contentions regarding the accident analyses contained in both the DES and the FES more than five years ago. Absent some credible showing why it failed to do so, NRDC should not be permitted to raise issues which properly should have been raised in 1976-1977. At some point, the issues in this proceeding must be narrowed and fixed, and the time-consuming and disruptive process of amendment and revision must cease.

l In addition to claiming that its challenge to the FES relieved it of responsibility to file contentions in a timely manner, NRDC also claims that subsection (b) of l

20/ See NRDC et al. Motion to Declare that the CRBR FES is not a Legally Sufficient FES and to Require that the Aforesaid Document Be Circulated for Comment as a Draft, April 9, 1977.

21/ NRDC did, of course, file contentions relating to the DES in a number of areas. (See e.g., Contentions 9 and 14). At the time these contentions were filed, NRDC apparently understood its obligation to file conten-tions in a timely manner.

Contention 20 is " based upon Commission policy, adopted in 1980, requiring consideration of Class Nine accidents in environmental impact statements, and it plainly could not have been asserted previously.- In making this assertion, NRDC has chosen to ignore the fact that Class Nine accidents were discussed in detail in both the DES and the FES. (See DES S 7.1, FES S 7.1.3.) NRDC's failure to submit contentions regarding the adequacy of those discussions is unrelated to the Commission's recent Statement of Interim Policy. Indeed, the Policy Statement itself specifically refers to and approves of the NRC Staff's consideration of Class Nine accidents in the Clinch River FES.

Moreover, the Statement of Interim Policy relied upon by NRDC is, by its terms, inapplicable to this proceed-ing. The Statement specifically provides that it applies only in those proceedings in which no Final Environmental Statement has been issued. The Statement also provides that absent a showing of "special circumstances" the Statement shall not serve "as a bases for opening, reopening or expanding any previous or ongoing proceeding." Inasmuch as l

22/ NRDC Revised Contentions at 36.

I

---23/ Nuclear Power Plant Accident Considerations Under The National Environmental Policy Act of 1969, (Statement of Interim Policy), 45 Fed. Reg. 40101, 40102 (June 13, 1980).

I l

l l

1 l

the FES was issued in 1977 and contains a discussion and analysis of the consequences of Class Nine accidents, there is no factual or legal basis for permitting NRDC's Conten-tion 20(b). Certainly, the issuance of the Policy Statement itself cannot serve as the basis for admission of a new contention.

Finally, to the extent that Contention 20 alleges that "[N]either Applicants nor Staff have adequately described the risks and consequences associated with CRBRP accidents beyond the design basis," it plainly duplicates matters already raised by Contentions 2, 3, and 4. Conten-tion 2 alleges that the envelope of DBAs (design basis accidents) should include the CDA (core disruptive acci-dent). Contention 3 alleges that the analyses of CDAs are inadequate for establishing that the site suitability acurce term bounds credible accident scenarios. Contention 4 alleges that Applicants' analyses do not assure that the DBAs will envelope the entire spectrum of credible acci-dents. Thus, if the Applicants respond to Contentions 2, 3, and 4, and demonstrate that the site suitability source term is appropriate, they will have shown that accidents beyond that design basis are not credible, and will necessarily have given adequate attention to accidents beyond the design basis. If Contention 20 does not duplicate Contentions 2, 3, and 4 in that respect, then NRDC must be advancing some

unresolved " hidden agenda" of accidents which are lacking in t specificity and basis. Thus, Contention 20 should not be admitted for the reason that it duplicates Contentions 2, 3, and 4.

1 4 CONTENTION 21 Applicants' proposed system for classifying and 3

categorizing postulated DBA accidents, as described in PSAR Table 15.1.2-1, is arbitrary, fails adequately to take into account actual U.S. and foreign breeder reactor experience, I and is inadequate for purposes of protecting radiological health and safety.

)

! OBJECTION:

The classification system which NRDC now claims is

] arbitrary and inadequate has been in existence in the PSAR since 1976. The event classification system was modified in

! 1981 to incorporate certain editorial and non-substantive changes. (Copies of the current and previous charts are

attached hereto as Appendix D). These changes are so patently trivial that they cannot provide a basis for admission of a l new contention. Having failed to bootstrap the trivial l changes in the classification system into a new contention, NRDC has also failed to offer any additional reason why this

contention was not submitted in a timely manner. While NRDC i

claims that the contention is based on new information i

[ regarding leaking welds in steam generators and steam i

i 6

> . ... r +.+ , . , - - - - - - - - - - - , , , - - . . - . - - - - , - - - - - - - . - - - - - - - . . . - - - - - - - - - ~ - - - -

generator corrosion, NRDC does not link this "new infor-mation" to any alleged deficiencies in the event classifi-cation system. Nowhere does NRDC explain why the system is deficient in light of this alleged new information.

Instead, NRDC merely advances the vague and conclusory statements that the entire classification system is arbitrary and inadequate. In short, NRDC has failed to establish any bases for its new contention. If the specificity requirement in 10 C.F.R. 5 2.714 is to have any meaning, and if Applicants are entitled to notice of the matters at issue, conclusory and meaningless contentions like Contention 21 must be ordered inadmissible.

In addition, to the extent that Cantention 21 alleges that Applicants' proposed system for classifying and categorizing postulated DBA accidents is inadequate, it duplicates Contentions 2 and 4. Contention 2 alleges that the envelope of DBAs (design bases accidents) should include the CDA, while Contention 4(b) alleges chac Applicants' analyses are not sufficiently comprehensive to assure that analyses of the DBAs will envelope the entire spectrum of credible accidents. Thus, Contention 21 should be rejected as duplicative. If Contention 21 reaches more than chis, 24/ NRDC Revised Contentions at 36.

then it improperly includes a " hidden agenda", and must be rejected as lacking in specificity and basis.

CONTENTION 22 Neither Applicants nor Staff have demonstrated that the design of the containment reduces offsite doses during accidents to a level that is as low as reasonably achievable.

OBJECTION:

Applicants oppose admission of this contention because Intervenors have failed to establish any basis for 4

the contention or to present any new information justifying its late submission. Intervenors claim that Contention 22 is "an elaboration of Contention (8)" and that they have merely " broken out the accident component to clarify that the ALARA concept must be applied to accidents as well as normal operations.- That statement, however, is clearly at odds with the holding of the Atomic Safety and Licensing Appeal Board. The Appeal Board stated in its 1976 consideration of the Applicants' motion for directed certification of the question of admission of Contentions 7 and 8:

Rather, as the Board below stressed, in their altered form both contentions go to the assessment of the radiological impact of the facility in normal 25/ NRDC Revised Contentions at 37.

i  !

operation assuming a compliance with all regulatory requirements.

Proj ect Management Corporation, Tennessee Valley Authority (Clinch River Breeder Reactor Plant), ALAB-330, 3 NRC 613, i 619 (1976) (emphasis added). Thus, as Intervenors are well aware, Contention 8 has never contemplated application of ,

i the ALARA concept to accidents.

In raising this issue in Contention 22, not only are the Intervenors attempting to introduce a new contention without any basis, they are also asking the Board to make policy for the Commission by applying the "as low as reasonably achievable" (ALARA) standard for releases of

j. radioactivity to accidents. The ALARA standard, however, i

applies only to releases occurring "during normal reactor

, operations." See 10 C.F.R. 5 5 50.34a(a) and 50.36(a). This i

! has been the policy of the Commission since those  ;

regulations were first published in 1970. As the Commission noted in Rulemaking Hearing on Numerical Guidelines for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Practicable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents , CLI-75-5,1 NRC 277, 285 (1975):

Existing Commission regulations have recognized the need for licensees to be permitted flexibility of operation compatible with considerations of health and safety to ensure that the public is provided a dependable source of power even under unusual operating conditions i

l l

that may temporarily result in releases higher than the numerical guides for design objectives.

(Emphasis added.) While the standard has changed from "as low as practicable" to ALARA to conform with the convention of the International Commission on Radiological Protection, j

the application of that standard, as stated in 10 C.F.R. 55 20.1, 50.34a, and 50.36 has remained the same, i.e., limited to normal operations. See 40 Fed. Reg. 58847 (December 19, 1975).

Even if the Commission were presently considering 26/

the application of ALARA to accidents,-- it has not yet adopted or developed any firm policy. Under these circumstances, it would be plainly inappropriate for the Board to accept this contention and the underlying policy in advance of a Commission decision. As the Board stated in South Carolina Electric and Gas Co. (Virgil C. Summer 26/ The Commission has issued a Proposed Policy Statement which considers the possibility of applying ALARA to accidents. The Policy Statement, however, is provisional in nature and has merely been submitted for public comment. Moreover, even if adopted, the Policy Statement will only be in effect for a " trial period." During the trial period, " individual licensing decisions would continue at present to be based princip' ally on compliance with the Commission's Thus, even if eventually adopted for a regulations.

" trial period," the Proposed Policy Statement will not form the basis for " licensing decisions." See Proposed Policy Statement on Safety Goals for Nuclear Fower Plants, 47 Fed. Reg. 7023 (February 17, 1982).

Nuclear Station, Unit 1), LBP-81-44 (Oct. 15,1981), when it was requested to adopt a new policy:

Moreover, even if we could agree with the suggested new policy, we lack the power to adopt it. In Offshore Power Systems, (Floating Nuclear Power Plants), CLI-79-9,10 NRC 257, 261 (1979), the Commission indicated that only it, and not the licensing boards (in that case an appeal board) was

' empowered to make policy as well as apply it.'

As in Contention 20, Intervenors also assert that, because they challenged a portion of the 1977 FES, they thereby have carte blanche authority to assert any new contention regarding the 1977 FES. As noted earlier, NRDC's challenge to the FES concerned the issue of national 27/

alternative sites-- while Contention 22 "is based on discussions of containment design in the 1977 FES." NRDC's bootstrap argument that its unrelated challenge to the FES can justify its failure to file timely contentions is unsupportable. If NRDC wishes to raise new and untimely contentions, it must establish good cause in accordance with the standards set forth in 10 C.F.R. S 2.714. Having failed even to address the factors in 10 C.F.R. S 2.714, much less establish good cause, NRDC's new contention must be denied.

27/ See NRDC et al. Motion to Declare That the CRBR FES is not a Legally Sufficient FES and to Require that the Aforesaid Document Be Circulated for Comment as a Draft, April 8, 1977.

CONTENTION 23 Neither Applicants nor Staff have demonstrated that the facility will be provided with systems necessary to establish and maintain safe cold shutdown and maintain containment integrity that are capable of performing their functions during and after being exposed to the environmental conditions (a) associated with postulated accidents, as requirci by General Design Criterion 4,10 C.F.R. Part 50, Appendix A; or (b) created by sodium fires or the burning (or local detonation) of hydrogen.

OBJECTION:

To the extent that Contention 23 alleges that Applicants have not demonstrated that the facility will be provided with systems necessary to: (1) establish and maintain safe cold shutdown; and (2) maintain containment integrity that are capable of performing their functions after being exposed to certain environmental conditions, it is (1) duplicative of Contentions 2, 3, and 4, and, if not, I

(2) unnecessary to an LWA decision.

Contention 3(h) specifically addresses containment integrity for site suitability purposes while Contentions 2, l

3, and 4 together address the relationship between CDAs, the appropriate CRBRP design basis, and the site suitability source term. It is thus clear that in the context of LWA l findings, it is not necessary to address Contention 23, beyond the issues already encompassed within Contentions 2, 3, and 4. If Contention 23 is not duplicative, and in fact i

l

has a broader reach to include issues such as means for establishing and maintaining cold safe shutdown, and equipment environmental qualification, then it not only lacks specificity and basis, but also raises issues which can clearly be deferred until the CP proceedings, or even the OL proceedings.

CONTENTION 24 Neither Applicants nor Staff have adequately described the additional features and requirements necessary to provide reasonable assurance that the CRBR can be constructed and operated at the proposed location without undue risk to the health and safety of the public.

OBJECTION:

As in Contention 20, NRDC recognizes that Contention 24 is not based on any new information but is premised on the 1977 FES. Nonetheless, NRDC again asserts that because it challenged the alternative site discussion in the 1977 FES, it was relieved of any responsibility to file contentions in a timely manner. As previously discussed in response to Contentions 20 and 22, NRDC's bootstrap argument is unsupportable and should be rejected.

Contention 24 should be rejected for the additional reason that .t does no more than state a legal conclusion without any attempt to establish a factual basis. Similarly vague and conclusory contentions have been routinely deemed inadmissible. In Offshore Power Systems,

supra, a number cf contencions were denied because they merely characterized various analyses as inadequate without attempting to state with particularity the bases for the contention. In this case, it is difficult to imagine a broader, more unfocused and conclusory assertion than Contention 24. Contention 24 does no more than assert that the CRBR cannot be constructed and operated "without undue risk to the health and safety of the public." It should be rej ected .

II. DISCOVERY NRDC has provided its list of: (1) proposed areas of discovery for new contentions and (2) new information relevant to Intervenors' contentions as to which it wishes to undertake discovery. The parties have conferred, and as a result, Applicants hereby state their positions concerning discovery.

A. Proposed Areas of Discovery for New Contentions In this regard, Applicants' general poaitions are:

1) Discovery should follow the scope of the contentions admitted by the Board.

2) Discovery should commence on a given conten-tion as soon as it is admitted by the Board.

Applicants' specific positions as to each new contention are as follows:

1) NRDC wishes to undertake discovery in regar,d to the rewritten part of Contention 3 as follows:

16. a) Details of Staff's and Applicants' analyses of the radiological source term, both as described in the 1977 Site Suitability report and any current or proposed changes.

b) Details of Staff's and Applicants' roposed method (s) for circulating p[ calculating] guideline values for radiation doses.

APPLICANTS' POSITION - Existing discovery on

' contention 3 will be updated. This would cover all matters of fact up through and beyond the time of the 1977 Site Suitability Report. Discovery should be allowed only upon current or proposed changes to that. info rmation.

As to the details of calculating guideline values for radiation doses, this relates to NRDC's old Contention 8 and NRDC's revised Contention 8(d)(1) and (2). Discovery should be allowed within the scope of Contention 8(d)(1) as admitted by the Board. Contention 8(d)(2) is the same in substance as old NRDC Contention 8. Existing discovery on that contention will be updated, and additional discovery should be limited to one round of follow-up on that infor-mation. (See also, Applicants' position in Section II. B.

4. below).

l

2) NRDC wishes to undertake discovery on its new contentions 16-24. The Applicants' positions are as follows:

16 and 17 - For the reasons stated in Section I above the contentions should not be admitted and discovery should not be allowed.

18 and 19 - For the reasons stated in Section I

above the contentions should not be admitted. In any event, discovery should be allowed on the contentions only within the scope of the contentions as admitted. Moreover, for purposes of LWA-1 findings, neither quality assurance nor emergency planning issues are necessary to a decision and both areas of discovery should be deferred to the subsequent j CP phase of the proceeding. Likewise, for purposes of an i

LWA-2 decision, the emergency planning issues can be deferred to the CP phase, and the scope of inquiry con-cerning quality assurance can be limited to the scope of safety-related work proposed. Thus, any discovery on quality assurance beyond that scope can be deferred to the CP proceeeding.

3) 20 through 24 - The contentions should not be admitted and discovery should not be allowed. To the extent that the contentions duplicate Contentions 2, 3, and 4, dis-covery should be allowed as appropriate under those conten-tions only. In addition, to the extent that it goes beyond

the scope of discovery on Contentions 2, 3, and 4, discovery on Contention 23 should be deferred until the CP proceedings.

B. "New" Information In Regard to the Intervenors' Existing Contentions In this regard, the Applicants' positions are:

1) Discovery should follow the scope of the contentions as agreed upon by the parties and admitted by the Board.

2) Discovery should commence on a given conten-tion as soon as it is agreed upon by the parties and admitted by the Board.

Applicants' specific positions as to each area of l

"new" information identified by NRDC in Appendix 1 to its February 9, 1982 Prehearing Conference filing are as i 28 follows:- /

1. Contention 10(g) - relates to analysis of alternative sites which may have more favorable environmental and safety features. The Commission has held that siting alternatives are relevant to this proceeding in order to determine whether substantially better alternatives 28/ In indicating aF eement that an area of new information identified by NRDC is a permissible area of discovery, Applicants can only agree, on a threshold basis, that the discovery would be permissible, if a particular request is in fact related to new information and relevant to and within the scope of admitted conten-tions. Applicants reserve their right to object in regard to particular facts and circumstances indicating otherwise.

are likely to be available to meet the program's informational goals. New information includes:

a. New meteorological data related to CRBR proposed site (see Amendments XI to ER, Section 2.6 and letters dated November 20 and November 30, 1981 from Paul S. Check to John R. Longnecker.)

b. Office of Nuclear Reactor Regulation, NRC, Report of the Siting Policy Task Force (NUREG-0625) (Aug. 1979) sets forth recommendations of a number of changes to current NRC policy on nuclear power reactor siting, including:

1. renewal of present policy of permitting plant design features to compensate for unfavorable site characterization in favor of emphasizing site isolation, and

2. use of selective siting to reduce the risks associated with accidents beyond the design basis (Class 9).

c. Proposed revision of NRC reactor siting criteria (45 Fed. Reg. 50350, July 29, 1980)

(Advance Notice of Proposed Rulemaking). '

d. Proposed rule regarding the review of alternative sites under NEPA (45 Fed. Reg. 24168, April 9, 1980).

e. Notice of Intent to Prepare an Environmental J Impact Statement for Revision of the l Regulations Governing the Siting of Nuclear l Power Plants (45 Fed. Reg. 79820, December 2, 1980).

I f. NRC, A Comparison of Site Evaluation Methods (NUREG/CR-1684) (July 1981).

g. These proposed rules arise from requirements of the NRC FY 1980 Authorization Act (Pub. L.

No.96-295, 94 Stat. 780, June 30, 1980) directing the NRC to develop regulations establishing demographic requirements for I facility siting. It also directed NRC to develop reactor siting criteria for new plants by specifying maximum population

dencity and population distribution criteria independent of differences in design among plants and that in developing demographic criteria a full range of accidents, including those beyond the design base accident, be considered.

h. New emergency planning regulations (45 Fed.

Reg. 55402, August 19, 1980). See also NRC and Federal Emergency Management Agency, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (NUREG-0654, FEMA-REP-1, Rev. 1) (Nov.

1980).

APPLICANTS' POSITION - Discovery concerning this item will be updated and discovery concerning that informa-tion should be limited to one round of follow-up on that information. Discovery on items b. through h. should not be allowed for the reasons stated above in connection with NRDC Contention 6 (demographic considerations).

2. Contention 2 - relates to the probability of core disruptive accidents, the adequacy of Applicants'

" reliability program," and the inclusion of a core disruptive accident in the CRBR design base. New information includes :

I a. NRC proposed rule recuiring improvements in l reactor design to rec uce the risks from I anticipated transients without scram ("ATWS")

events (46 Fed. Reg. 57521, November 24, 1981).

b. Critiques of the Reactor Safety Study, Main Report, U.S. Nuclear Regulatory Commission, WASH-1400 (NUREG-75/014) (October 1975)

(Rasmussen Report) -See Risk Assessment Review l Group Report to the UTS. Nuclear Regulatory Commission (NUREG/CR-0400); Nuclear Regulatory Commission Statement of Risk Assessment in Light of the Risk Assessment Review Group Report, Jan 18, 1979.

4

c. Implications of the TMI-2 accident, particularly regarding the effects of human error on failure to scram:

See U.S. Nuclear Regulatory Commission, NRC Action Plan Developed as a Result of the TRI-2 Accident (NUREG-0660) (Aug. 1980) ; U.S.

Nuclear Regulatory Commission, Identification, of New Unresolved Safety Issues Relating to Nuclear Power Plants (NUREG-0705) (March 1981);

See also Letter, dated January 27, 1982, from IIchard Shikiar, Director, Social Change Study Center, to Dr. Thomas Cochran, NRDC (discussing presentation of Harold Denton, Office of Nuclear Reactor Regulation, NRC, at Peer Advisory Panel meeting concerning qualifications of nuclear tv,rer plant operators).

d. Discussion on pp. 120-121 of DOE's draft supplement impact statement en the LMFBR program describing research and testing programs that have occurred since 1975 (particularly reports listed in footnotes 1 and 4 on p. 141 of draft).

e. New Commission studies on appropriate safety goals; e.g.:

(i) U.S. Nuclear Regulatory Commission, Workshop on Frameworks for Developing a Safety Goal (NUREG/CP-0018) (June 1981);

(ii) U.S. Nuclear Regulatory Commission, Toward a Safety Goal: Discussion of Preliminary Policy Considerations (NUREG-0764) (March 1981);

(iii) U.S. Nuclear Regulatory Commission, An Approach to Quantitative Safety Goals for Nuclear Power Plants (NUREG-0739) (October 1980).

APPLICANTS' POSITION - Discovery might be allowed on items 2a. and 2b. to the extent that it seeks information relevant to CRBRP. Discovery on item 2c. should be allowed

only to the extent that the contention is admitted, and then within the scope of the contention as admitted. Discovery on item 2d. might ba allowed to the extent that it seeks information relevant to CRBRP. Discovery on item 2e. should not be allowed for the reasons set forth above in connection with Contention 22.

3. Contention 3 - relates to Applicants' failure to establish that the consequences of core disruptive accidents are adequately described in the PSAR. New information includes:

a. Applicants have modified the computer codes used to simulate accidents to determine their potential and magnitude. See PSAR Section 12, Appendix A; p.121 of DOE Draf t EIS Supplement; and letter, dated January 22, 1981 from Paul S. Check to John R.

Longnecker.

b. There have been significant changes in reactor vessel and core design that must be reflected in Applicants' accident modeling (See, e.g., PSAR Sections 4.1 and 4.2).

c. New results on ongoing safety testing (see pp. 118-135 of DOE EIS draft and footnotes 4, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, etc .

on pp. 141-144). See also General Electric, An Assessment of HCDA Energetics in the CRBRP Heterogeneous Reactor Core (December 1981).

d. List of unresolved safety issues at time of suspension of CRBRP licensing proceeding:

Letter dated November 9, 1978, from W. P.

Gammill to L. W. Caffey, " Summary of Outstanding Items."

e. New Regulations, e.g.:

(i) " Licensing Requirements for Pending Con-struction Permit and Manufacturing License Applicantions" (47 Fed. Reg. 2286, January 15, 1982). Based on Commission's effort to apply lessons

learned from the Three Mile Island Accident as reflected in "TMI Action Plan" (NUREG-0660) and " Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License. March 1981.

(NUREG-0718) (Rev. July 10, 1981).

(ii) Proposed rules to require improved hydrogen control capability during and following reactor accidents (46 Fed.

Reg. 62281, December 23, 1981) (see also 46 Fed. Reg. 57521, 47 Fed.lGhi.

TIBT).

f. Criticisms of the Reactor Safety Study, Main Report, U.S. Nuclear Regulatory Commission, WASH-1400 (NUREG-75/014) (October 1975), see Section 2(b), supra.

APPLICANTS' POSITION - Discovery might be allowed on items 3a. and 3b. , limited to one round~ cf follow-up on ,

updated discovery information, and on items 3c. through 3f.

to the extent relevant to the admitted contention and to CRBRP.

4. Contentions 7 and 8 - Health Effects from Plutonium Exposure:

a. New report: National Academy of Science.

The Effects On Populations of Exposure to Low Levels of ionizing Radiation (National Academy Press 1980) (BEIR Report)

b. Reassessment of the magnitude and effects of neutron dosages at Hiroshima. (See, e.g., W.

l E. Lowe and E. Mendelsohn, " Revised lose

! Estimates at Hiroshima and Nagasaki" (UCRL 85446 preprint, 1 October 1980), available l from Lawrence Livermore National Laboratory).

c. Three years of new results from ongoing beagle experiments (see, e.g., Pacific Northwest Laboratory, Richland, Wash., Annual l Report for 1979 to the DOE Assistant Secretary for Environment (February 1980),

and Cross, Palmer, Filipy, Dagle, and Stuart,

" Carcinogenic Effects of Radon Daughters, Uranium Ore Dust and Cigarette Smoke in Beagle Dogs." (Pacific Northwest Laboratory, Richland, Wash., April 24, 1981).

d. John W. Gofman, Radiation and Human Health (Sierra Club Books, San Francisco 1981) (1000 P.).

e. NRC revisions to Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will be as Low as is Reasonably Achievable." (NRC Office of Standards Development) (Rev. 2, March 1977).

f. Changes in Applicants' Radiation Protection Program (see PSAR Section 12, Amendments 40, 44, 45, 49 and 52).

g. New Regulatory Guides related to radiation protection, listed in letter, dated January 13, 1981 from Paul S. Check to John R.

Longnecker.

APPLICANTS' POSITION - Discovery will be updated. Discovery should be limited to one round of

! follow-up on in that information as relevant to CRBRP.

5. Contention 4 - relates to Applicants' analysis of accident possibilities of greater consequence than the design base accident, such as accidents associated with sodium-concrete interactions and core catcher failure. New information:

a. The Applicant has conducted an analysis of such accident possibilities (see Appendix C to DOE's draft supplemental LMFER impact statement, Excerpts from CRBR Safety Study, CRBRP-1, March 1977).

b. New data related to an LMFBR's ability to l accommodate core debris following a core

! disruptive accident (see, Je. ., footnotes 36, 37, 39, and 40 on p.17CT or DOE draf t supplemental LMFBR impact statement).

c. Critiques of the Reactor Safety Study, Main Report, U.S. NRC, WASE-1400 (NUREG-75/014)

(October 1975) (Rasmussen Report) (see Section 2(b) supra).

APPLICANTS' POSITION - Discovery will be updated. Discovery should be limited to one round of follow-up to the extent relevant to the contention and to CRBRP.

6. Contention 9 - relates to the environmental impacts of the fuel cycle facilities associated with the CRBRP:

a. New proposed leg'.olation and proposed regulations on sating and construction of waste disposal facilities (see 46 Fed. Reg. 35280 (July 8,1981; 46 Fed. Reg. 221 ovember 15, 1981).

b. New regulations on transportation of high level radioactive wastes: 45 Fed. Reg. 7140 (January 31, 1980); 447 Fed. Reg. 34446 (June 15, 1979),

c. New studies and Administrative initiatives on (see, potential for commercial reprocessing"NucTear Je.., Starement of President Reagan, c Energy Policy," 17 Weekly Comp. Pres. Doc.

1101-1102 (October 12, 1981); Minutes of April 23, 1981 Meeting between DOE and Nuclear Industry Representatives Concerning Potential for Commercial Reprocessing (statement of Brian D. Farrow, Senior Vice President and General Counsel, Allied Com-l mercial Corp. and W. Creighton Galloway, Exec. Vice President, General Atomic Co.,

l " Prospects for Private Investment in Nuclear l

Fuel Reprocessing.")

d. Dramatically increased weapons program may limit the availability of fuel for the CRBR (see, e.g., Hearings before the Senate

) Committee on Environmental and Public Works, l

Subcommittee on Nuclear Regulation, December 8, 1981 at p. 3).

1

APPLICANTS' POSITION - Discovery should not be allowed on items 6a. through 6c. for the reasons set forth in the Board's April 6, 1976 Order in regard to Contentions 9 and

12. Discovery should not be allowed on item 6d. for the reasons scet forth in connection with Contention 17 above.

7. Contention 5 - relates to the health and safety consequences of acts of sabotage, terroriam or theft directed against the CRBR or supporting facilities.

New information:

a. Changes in Applicants' safeguards program (see pp. 145-172 in DOE's draft supple. mental LHFFR impact statement) .

b. New NRC regulations on physical security (10 C.F.R. 5 73.55, " Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage).

c. Department of Energy, Nuclear Proliferation and Civilian Nuclear Power: Report of the Nonproliferation Alternative Systems Assessment Programs (DOE /NE0001/7) (June 1980).

d. Proposed NRC rules concerning material control and accountability requirements for licensees processing special nuclear materials (46 Fed. Reg. 45144 September 10, j

1981 (advance notice of proposed rulemaking).

e. Several recent GAO reports concerning safeguards and physical security.

(i) " Security at Nuclear Powerplants -- At Best, Inadequate" (4/7/77).

l (ii) Unclassified summary of a classified report entitled, " Commercial Nuclear l

Fuel Facilities Need Better Security" (5/2/77).

(iii) Letter to Chairman, John Dingell, U.S.

t House of Representatives, Re: unaccounted for l

nuclear material (5/5/78).

- - - - , , - - - - - - - - - - _ _ m--.-

(iv) Unclassified summary of a classified report entitled, " States of Physical Security Improvements to ERDA Special Nuclear Material Facilities" (9/8/77).

(v) " Federal Actions are Needed to Improve Safety and Security of Nuclear Materials Transportation" (5/7/77).

(vi) Unclassified summary of classified report entitled, "U.S. Nuclear Safeguards -- A National Strategy is Need ' (2/19/80) .

(vii) " Nuclear Fuel Reprocessing and the Problems of Safeguarding Against the Spread of Nuclear Weapons" (3/28/80).

(viii) Letter to Rep. Tim Wirth, Re: Alleged missing material from DOE's Rocky Flats weapons production plant (10/1/80) .

(ix) " Nuclear Diversion in the U.S.? 13 Yearn of Contradictors and Confusion" (12/18/78). Classified report with no unclassified summary.

f. Staff and Applicants have both conceded that changes in " dynamic factors at work in society" may necessitate changes to present and currently foreseeable security requirements. (See, e.g., Staff answers to Part III, Interrogatory No. 7 of NRDC, et al.'s Sixth Set of Interrogatories to MEC 3taff).

g. International Atomic Energy Agency, International Fuel Cycle Evaluation (Vienna, 1980).

APPLICANTS' POSITION - Discovery should be allowed on the contention only as admitted and subject to the Board's April 6, 1976 Order admitting the contention and limiting its scope. Any examination of fuel cycle impacts should not go beyond the scope of existing NRC regulations,

and should not involve a licensing review of DOE facilities which are not subject to NRC jurisdiction.

8. Contention 14 - relates to the unavoidable adverse environmental effects associated with the decommission-ing of the CRBR. New information:

a. Recent evidence indicates that permanent entombment may not be a viable form of decommissioning, since some reactor components will contain extremely long-lived isotopes of nickel and niobium. (see "A Long-Term Problem for the Nuclear InTustry,"

Science, Vol. 215, January 22, 1982).

b. EPA is preparing rules that would permit ocean dumping of low-level radioactive wastes. (see " Agency May Alter Atom Waste Policy," TGsi York Times , January 15, 1982).

c. The Navy has issued a Notice of Intent to Prepare an Environmental Impact Statement on its plan to dispose of retired nuclear submarines in the ocean. 47 Fed. Reg. 2151 (January 14, 1982).

APPLICANTS' POSITION - Discovery on item 14a.

should be allowed only in regard to Niobium. Discovery on items 14b. and 14c. should not be allowed as those areas are not relevant to CRBRP.

9. Contention 6 - relates to meteorology of CRBR and alternative sites:

a. Applicants have developed new meteorological data. See ER Section 2.6, Amendment XI, letter, dated November 30, 1981 from Paul S.

Check to John R. Longnecker.

APPLICANTS' POSITION - See Applicants' position in regard to paragraph la. above.

57 -

For the foregoing reasons, the Board should adopt the Applicants' positions in regard to the admissibility of contentions and discovery.

Respectfully submitted, h

Warren Bergholz Attorney for the ///r//

Department of Energy sms W GeoYge-(E.' Edgar g' Attorney for Projrct l

Management Corporation Dated: March 19, 1982 l

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A unique operation of the Metal Preparation Division is 7 d$

   '                        to process large quantities of enriched uranium into 7.,

forms suitable for fabrication. In a typical production  ;. [' l .-J cycle, U-235 compounds are converted to metal, cast or t

    '                       rolled and formed into appropriate shapes, then                          '                             '.

M #A . - i machined to final dimensions. Throughout this cycle, the many forms of U-235 waste products are recycled to recover every salvageable amount of this valuable

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                                                                                                                                        ',   '"                                    I material. Extraordinary handling, transporting, storing, and accounting methods are utilized for U-235 for two
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                                                                                                                                                                                      . ;,i, principal reasons: it is a fissile material, and it is worth                        "           *
                                                                                                                                  - - -                                                 4' several times its weight in gold.

h M . s Ja dty k ses . W e. , Chemical processes for production include: manufactur- .3 i ing compounds and plastics, converting compounds to _ sed.dgn.1.., himSmE , .u o m - iu m n 1.. .3 .n 1 g; elements by chemical and/or thermal reduction, manufac- _ turing elastomeric containers, and purifying compounds

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ypi 3 Vp The Fabrication Division's prin)e responsibility is to mach.no M lNg-:i J.L.

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' nuclear weapon components. .

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h tools. Common matarials can be machined to extremely close..M* 'M y ' ' * j Ny?',f(; [ j,. i '. tolerances; and hard materials, such as aluminum oxide, can G. . .i g g; Jj j i j ,.h "j , 4(. d F be ground to exacting tolerances. Machine tool accuracles of j ;; ;g.: .m ys

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p:,((ll4 ! 600 microinches are achievable oni. many of the tape-controlf't l .M,. . . ,rm C * . h,b,,, ypr) ' i . Nl(D g ';r'rW" .

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                                          ' Fabrication  turning  Division      machines.

ranges frpni.less Size of the[ than one-half parts loch to.Ji handled by M{f';the - j O Ni L i S  ; l i - Demands for CIose-tolerance,'hlgh Securacy m4 chining have'l'i ,p . , ,,. df.

                     .,     h, .';piresulted in . the ConstTUCtion of . machine shops where rh. - d a f a                                                                                                    . . ,,. _ .. ... .. ,..j e f . A p . W ih. :,; 5 .-i,( (          .                                              .j
            'N                                                                                                                                              /W'                                                                                                                                                          VM_

D temperature and humidity conditions Dre closely malatained hin order to produCS high-quality preci$lon i Y 12parts. machines used Part la fatwicathissupport special keyne'.Agl'N.h,Jg; pres oop pr several the Houomal; y techniques are being developed to ic. Aeronautics and Spec 9 Adrninistrodon's Apoth pogress.Qaq:or minimize the.,3

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                           .[h             ,5the     finished part due to fixturing and part weight. Numerous.-                                                                        l }.y . :4'4                           : .F : . . f .                                                             t        .,          ;].

lf/' f l k musammmmmmmmmmmunq ,

                              %.y jfeedback   h state-of.the-art"                                   machines                   employing                       laser interferometer,h       ypp.t l

0 and air-bearing spindles are presently being the Fabrication Division;toiproduce :perts, having closef/ 4 . used in g.h.h{h {M,']f. p ;gy .

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7 V .M.d': [l Materials fabrication operst$ns such as shearing,; forming,hf phhh/ h [7. j '

1.i.d h.K $ . 6-1 k Z 3- 3

                                                                                                                                                                                                                                                                                             -p~                       '

d D h.and welding machining Nontraditional' aspport operations the overall 'such Plant: fabrication as electrical . mission. ' =

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J 'N  ;.j discharge rpachining ' and chemical,in i g k{p'dh [the . Plant's primemachinin T! :.V l 4 hincreasingly utilized. Involvement $ %'f. 'l,:f,Ny [ p.sp g'.  :",4

                                                                                                                                                                                                                                             )Q'y l
                                                                                                                                                                                                                                                                              .i "i[k                        q,                 y ypa ;p.         '[j Jactivities     el responsibility                                               for weapons manufacture                                                                           g lr,Cigdoes                 Mc,&; not            g ,,iqpreclude.
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in. other areas of metal removal. Sufficient F %M lng L l : quantitles of each machine type are available to permit the$

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                                        < fabrication                    of jobs of       .e the ."one-of-a-kind"..                      variety... 7 .. p t                                                            .
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N h.. . N Through the years, Y-12 fabrication support to the Oak , b 'q Ridge National Laboratory, and, occasionally, to other a ,I

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variety of items. For example, Y-12 made many of the i 'i '.i . .

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components for the ORNL's ORMAK (below), a facility to < '- i be used in experiments of controlled thermonuclear fusion.

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  .      At the top right is a view of the heat exchanger for the Molten Salt Reactor Experiment and, at the center, the l.

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l Fabrication of this unit required over 4,000 precision welds, i .1 .; pJ . i .'{b i ,t  ; many of which were performed by semiautomatic welding

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tolerances. These skills must be accompanied by a capability } gt g'1 - ={ for varied and very precise measurements. Through the years " ~ the Plant has established controlled environments, procured f',. . .i "' n 3 advanced measuring machines and instruments, and recruited and trained skilled personnel to provide a capability that j, Aboa, a awawicany mnesotied, two-exis dimen-

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l small hand-held gages for bench work to highly sophisticated ^ g F and computerized measuring machines. 3 .,, _ Tq -

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To ensure the continual quality of Y-12 measurements, the g ,g j Plant maintains a Gage Laboratory and a Physical and j

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{. inspection and calibration, but periodically reinspect and 1-iQ y ,3 j recertify all such equipment. ,

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l' .. : D if 's . f Metal parts are joined by such processes as the gas-tungsten- ]{~ , N i1 -a' arc, vacuum and atmosphere electron beam, laser, percussive, } .lg, Y E~ ultrasonic, and resistance spot welding. An automatic, f , I J gas-tungsten-arc-weld system can be programmed to make s j.; i) ' p five types of welds. The system programs the workpiece hj . . . position, torch position, arc oscillation, voltage, current, gas Jj Y (

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((., j . Assembly personnel fabricate very strong, light-weight ,,.

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1 structures using numerically controlled filament winders, one j g ,jp';,,,, g . M & iT' h of which is a four-axis machine. These and other components ,, are dried and cured in ovens with programmed temperature cycles. ,

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li ' There is an intensive program to assure the quality of materials and operations. This activity includes the !i disassembly and collection of samples from production it s l{ in order to evaluate product quality. , l g'" O. .h 8. (:. : Ul

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• f3 One of the largest weWing units bi Y-12 is this autoenetic weWer, atMne right. 'Ihe laser weWer, below right, can weW I

I , Q l .. j l.,; .' adnisture cosnponents through any transparent snaterial. a h ; !.

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J PRODUCT ON SUPPORT s The production tupport divisions of the Y-12 Plant supply the necessary assistance to the .! i production divisions to accomplish the Plant missions. , i The Product Engineering, Maintenance, Shift Superintendents, and Administrative Divisions  : are responsible directly to the Y-12 Plant Superintendent. The Development, Technical, and .I

                                                                                                                                                              ';            i Engineering Divisions have the dual responsibility of supporting missions of the Y-12 Plant and the Oak Ridge Gaseous Dif fusion Plant; and, thus, are responsible to the general staff of i-

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Union Carbide Corporation's Nuclear Division, .q t l A DEVELOPMENT-b _

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! Product Engineering and Scheduling s1: I . q*r l The Product Engineering and Scheduling Division i yg g . yh '.i I, provides a variety of coordinating services in support h i . : i 3.4 d I' of the Plant's fabrication mission. As its name " indicates, the Division determines how a job may best .,

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                                                                                                                                                                                               '*                                                                                    -h be performed to meet the technical specifications of                                                                                               g.3                  ,...                        ,
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I the customer and coordinates the flow of the job '

                                                                                                                                                                 .c3 ' '  s;. n                                           Eh                               ly                             l through its production cycle to meet the requested                                                                                                                           ' 3?/ ;'                    i         l   - -

fj li schedule. 1i71" 1 .- l t - i I 0

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• ms .N When a task is assigned to the Plant, the Division ' l.

must confer with the production divisions to - )g i k d - *

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                                                                                                                                                                                                                                                                    ;i. .               I determine the types of material to be used, the                                                                                                                                                           .n.

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the inspection techniques needed to certify the .y' "f : dg*?:i'.(Q. +7-product, and must then schedule these operations to -

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t ensure an orderly product flow. Critical path < A* g 4 scheduling techniques are used to ascertain that the , , . . . . , , , , , , , . ,, ,, .,, ,, l

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Job will be accomplished in accordance with .

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predetermined schedules. Often, such schedules must

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be made to coincide with the production schedules of

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9 h'h, . *- other AEC production plants involved in a different f ' ' .J , j .i ' D

                                                                                                                                                                                                                                                  ;;y pi :9 il      N l' phase of the fabrication project.                                                                                                                                                      Di                       e hf f', k .t $i . d f}dhh 4.nc'                                            .                                   'f h

After setting a job in motion, the Division maintains a j- er g . 'p - 1[.d.

. 4 o .Ik close liaison with the production divisions to move (l. i h .~ '

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! the job efficiently through its production cycle. This g 'h 7

' If i coordination is achieved through field monitoring by Division personnel and by a computer system which r,

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l ]: Packaging of a smitical component is performed on a laminar-now work bench, above right. Product quality is potected through the use of laboratory costs, shoe covers, white gloves, and appoplate ,' , l operating pocedures. Below right, a product engineer guides the peparation of a drawing for a special , l l poduction component. E ---- - - _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l lH,

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                                                                                                        ===                                                             c            j ,3                 gn- .g modifying present equipment, systems, and materials

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di II , Tha Division, statfed by approximately 200 scientists and engineers and 60 technicians, is organized into six Il,jI];g,,g;, ii g,;, , p ,4, t,

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major departments: Ceramics and Plastics, Chem- p ., - ':,s - istry, Fabrication Systems, Laboratory, Materials Jg{.h(9l nusuu== j f Engineering, and Metallurgy. Task groups which cross lll ll

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h ', - departmental lines are used to attack problems when f,g p.... j{.] .r*g{g}{(.3 1 i - l q' , 4/ i j - 1 l.Q ' l a concerted, cross-disciplinary offort is needed. 1- -

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[ ' h 44WM9&M as ceramics and plastics , , , , , The Ceramics and Plastics Development Department is concemed with ceramics, plastics, adhesives, and electroplat- i i ing problems as they are applied to the fabrication of special q materials. In general, conceptual studies of an experimental l or theoretical nature are performed, then scaled up and j optimized. From this design, criteria are established and j p assistance is given to the production divisions during startup. The Department is equipped with a number of unique l facilities which include a controlled humidity laboratory ' which has its own isolated support system for handling toxic g,-.-l:...,'..27;1-/7,' _ 7. 1.. [. . -[l X ' [ , materials. Many glove boxes with controlled atmospheres; a large number of presses with controlled temperature and humidity; various pieces of equipment for processing rubber Above, a photomiaograph of nickchteted usanham showkg the rough etch marface sequked for mechanical bonding the and thermoplastics, such as extruders, drapeformers, mills,

                                                                                            '8***' P3 *'*d n and presses; and a small electroplating facility are also                                        ,,[ a iow, a chamist mlan an adiseme utilized.                                                                   ,                                                                   ,
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                                                                                                                                                                 .j Equipment made by Ceramics and Flastics personnel for use in NASA's Apollo program. Inchaded are a braided Teflon lanyard, documented                         ,"

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I A major effort of the Fabrication Systems Development Department is r$ pr*r " '

                                                                                                                                                                                                                               "d                  6                 ( .I                 ' j ,f i 7

l directed toward the development of improved machining and inspection / ,

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i { .l,' j . 11 technology. For example, ultraprecision single-point machining technology is [;,f(,{,,. t 9A- I .{ %E r >

    'F,.'lbeing developed that can provide optical quality surfaces, and a numerically ,,. {,                                                                                      ,y         .'                                             ,j       .                         ,' M ,'! .

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          ' icontrolled lathe has been linked to a computer so that dynamic data on'                                                                       !j.,,,~                                                                                                    ,

machining and machine-tool performance can be collected and enalyzed.

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i .I mproved l methods for workpiece support while machining have been 1j. .

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( 2;' developed which eliminate dimensional changes when the piece is removed .

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l 4: ( from the machine tool. New techniques for material removal are being .. t ,! . .b,U 4' . I k j$ developed, such as ultrasonically assisted ' single-point toois to machine h h very  :) L'$ , '

                                                                                                                                                    . ,hd                                                                                     ,

[y.hrrd surfaces. s 7 ;,; p';1 'g

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                                                                                                                                                             .                   j    '                                                                                           ;e i , ' A significant effort of this Department is directed toward the development '                                                                         ?, . #           ~                                                                                 <%        j                          t; - '
        .gof composites utilizing a continuous filament of glass, boron, graphite, .                                                        ,
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         .porganics, or metals combined with organic resins or metallic matrices. Such
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      ;4 mzterials are designed into high-efficiency structures sustaining high servicetil06ds                                                                                       1                  e i
                                                                                                                                                                                                                     ,           .$                      or deflections with minim         '

j ' materials suitable for potential defense application, but bould be applied in' d ':j,i.Q:;;. @ l i 3; f.I

                                                                                                                              .*       ; ' O , ,,,! ?, q i                            I                                                                                  p W.other orgas,                                                                              ,    .   ,,                                                                    ,

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h. unique facilities include: a laboratory which , incorporates a closely t

    . licontrolled environment for precision machining and inspection and                                                                    ( hi;i.;,ylf-

{'(Integrated facilities for machine tool testing, machine component testing, .d [gg lSgih ' m g ( i

                                                                                                                                                                                                                                                                                     ,            5 'gg
                                                                                                                                                                                                                                                                                               ,- '. f 'T.:.'               i je I; machine                       control development, fabricating continuous-filament                   composite        and       machinability structures          with the shape      studles; of                    equipment f:
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ilot-plant I-4; utilizing virtually any on product figure of revolution; and p/ facilities.

                                                                                                     i           '

i .: k & ., , F-M f [ 'h..,I.'... -type, operating groups . J ;I h,i i t [jr mil 3 ,I 'N N 2 I

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g f.k.d@!hbig - (: O H . F t :T $ -[ 3 JL ; g % D y T.,1 Y~ Atmo risht, a numerically mntrolled L J'" 5

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                                       . l'                                                 k*rremn=ler, air twerlass, and wher                                                                                                                       .

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The Laboratory Development Department supports the f h.Y.- 3" 4 I y production divisions charged with the responsibility for 6, I 'l 9! , specification and certification measurements. This support d' may involve the development of methodology or design and fj , t

                                                                                                                                ."             --L         h w     f,          j fabrication of instrumentation to facilitate a desired                                                                                                 f ,         -j measurement. In addition, some instrumentation and                                              .

expertise are maintained for specialized, direct investigations {/. ? I.1 *9).- i, CO i

g.

where routine production facilities are not warranted. These facilities are particularly suited to the support of the e-Ne:d 4' ~ Jj

                                                                                            ,I                             ~

materials and fabrication development activities of other - T .' E I 4 i -g-r departments within the Development Division.

                                                                                                            *                                       -    M ~                 -

Unique facilities include an ion-microprobe mass analyzer ' N which is capable of determining chemical compositions, ,; - chemical distributions, and isotopic ratios across solid ' ?,, - l specimen surfaces with an areal resolution of two M k f g)f

                                                                                                                                                                         .y.

l micrometers and a depth resolution of about two angstroms-l and equipment to provide a wide range of physical propert , l over a broad spectrum of temperatures such as electrical l Typical or hboratory development equipment are the lossnicroswobe anarym,' ' resistivity, specific heat /enthalpy, thermal conductivity, above, the election microprobe analy=, below left, and the automated samme thermal diffusivity, and thermal expansion. counter, below.

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The Materials Engineering Development Department is responsible k g' I g (I 'ki for generating specific new materials for nuclear weapons programs. H f. 4-While the chief technical concern is with nonmetallic systems, [- - "' '1. I 'i. j , specialties such as metal powders, intermetallic compounds, and '

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                                                                                                           i' some ceramic materials are investigated to develop these materials for                                                                                                                                          $
                                                                                                                                                                                                                               '!   I specific applications. The Department also provides technical support                  l' '                                                                                   I'
                                                                                                                                                                                                                                  , ' j, to the production chemical processes employed for the recovery of                    P'                                     ~,o b              :'       ,

f i'-  :;, high-assay uranium from salvage streams and the control of waste I '3 .'!j l ':'%i  ;

                                                                                                               ,g,.-

materials from the Plant to the environment. r 'Q l h ' g A high degree of technical expertise exists in the specialized field of 5 j carbon and carbon composite structures. One development program gl 2'  !, {*, i is unique in that it has one of the most advanced carbon composite i*'

                                                                                                                                                                                                                  ;      O                        !i fabrication facilities in the nation. In part, this is made possible by access to an extensive array of high-temperature furnaces, W'i '.[I.{}'Mj3,M               .                                              i'g _2_M,kj                                                          j high-pressure impregnators, and other specialized fabrication                                    Below left. the modular dry-box system used in handling pyrophosk                                                                         le mainials that oxidize rapidly in air. Above, are samries of speciarty equipment capable of specimen-size or full-scale objects,                                        graphite grades developed and fabrkated at Y-12. Bekw, a drawing of                                                                        ;

the vacuum-essisted layup technique for fabricating carbon fibers hto' . . i shapes. >

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metallurgy p g.

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d The Metallurgical Development Department supports the

                                                                                                 , . l}M                                                                   '

(' g weapons production programs through the studi' of f\g .

                                                                                                                                   ,                   f'd* N                '

r' % ' metallurgical problems arising during weapons design, testing, O D ..

                                                                                                                  /"                   kh[ sE '           -

and production. This group develops materials with PM 3' e

                                                                                           ,                                    yf properties tailored te meet specific physical and mechanical                                          ..             -Cb'3/i   % 'I .D I

Ih.: ' requirements, and studies these materials to deterreine #.' l

 ;         methods of processing which will achieve optimum quaiity.                                  ']       ;                .y                                                  g Maximum yield, economy of materials and labor, and
                                                                                                               ;      [.
                                                                                                                                           ,,j              'p compatibility with the equipment available are also p
                                                                                                            . -   i                    .
                                                                                                                                       . .1p--       .             I'ge-                        ;i r           considered objectives.                                                                                                ' . J D       . -

LwA k Several areas of technical expertise are maintair.ed, including j' ! melting and casting, utilizing equipment for vacuum melting, .

                                                                                                                                                                                             'I slag melting, arid electron-bearn melting; metal working, using                                                                                                                   ,;(

forging, rolling, deep drawing, spinning, and high-energy-rate forming; metal joining, including electron-beam, arc-resist-l'} ance, ultrasonic, md laser welding, and brazing processes; and powder metallurgy, utilizing liquid and solid-state sintering, mbw kn, a

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die pressing, and hot and cold isostatic pressing and sintering.  ! I [,

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El l' Techuical r I 1 i :I l i

 ,                                                                                                                                            I' l          The Technical Division consists       the following departments: Quality Control, Data Systems, Criticality Studies, and                '     '

Radiation Safety and Industrial Hygi  ; i g The Quality Control Department is desi x -

                                                               ,to serve as a monitor and coordinator of the Pland quality control f

l procedures. It operates independently of the p ction and product certification organizations to permit an objective ., analysis of these operationt , The Data Systems Department supports the management a oduction-control-related system througis systems analysis I and design, programming, and computer operations support. , I l - i: ' Efforts of the Criticality Studies Department are directed toward thr ad areas of vital concern to the Y 12 Plant and fi to the nuclear industry in general: (1) basic reactor physics studies, (2) [eactor design studies, and (3) investigating , and generating data applicable to the nuclear criticality safety program. 1 ! The Radiation Safety and Industrial Hygiene Department provides services to preven to Plant personnel or to the i natural environment from potential dangers arising from the Plant's industrial processes. h l i g i \ , l f.

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ha quGlity C0Rtf0l b ' N 6 I I @ Y U b ~ Y .I I l k N N 4 - kih<, .:L~i

                                                                                                                                                              ' y-y This Department's role as monitor and                                                                                 . , ,, ,

coordinator of the Plant's quality control procedures is accomplished by several meth- i

                                                                                    ~

g(,. i ods. One method is to conduct statistical ,.f.o.,t . .,. ;;/ r, y

                                                                                                                                                                                           ..                           M i.r"'                  r 5 Ad analyses of production and inspection tech-      ....,ff niques to locate possible flaws in procedures
                                                                                         ~
                                                                                                                                                             . dO{$fLbNU                              L                 '

and to improve efficiencies. Another means is ,; , l by auditing product certification records and c ia, . tion or sases and instanwata ==d la thisc e certi. y

                                                                                                      **** I ' *8*'Y. *'" *"d k3'"'                      *" d *'3Y " *d'*

arranging for periodic reinspections of pre- to the Netk>nal Bureen of Standards, viously inspected work products to ascertain that quality specifications are being followed. .

                                                                         '                                                                                                                                        1'
                                                                                                                                                            ._ h                         '{-

1 e . p.g - ,) . . .o.31  ; ji ,,' ! , f ,:; f 3 The Department also maintains a Dimensional $l' . i i Inspection Laboratory used to certify the Plant's dimensional gages and verify items g

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                                                                                                                                            ] .:-y[. [..,lC.C Y;.i[iN((fi.hj ;,   I? i                 E
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supplied by vendors. Additional responsi- ,,_ . ji'. - * . {I .g q bilities include accounting for and processing ,, all documents relating to special nuclear ,

                                                                                                                                                                                                       ]J,.

materials, including receipts, transfers, and , , 1, 5 .- . . . l.

   '      inventories,                                                                                                                i                                                    ,

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i f dGlG Syst0MS ~ n g j :; ; g . g Th2 production control system consists of data collection .

                                                                                                  %              %           .                    i'*j'                      Uvf i                '       ' -                              '

activities through a network of input stations interfaced to

• Lt  ; .1 the computer that feeds this and most other systems; daily h uara,mser, . me, - j4 '

updating and reporting status, priority, inventory, and various other activities; periodic production summary

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                                                                                  -             r J

l ~ reporting; and an on-line inquiry system that is updated twice _.f f ' J1 I d:ily. Other important systems function as described in the q; subsections that follow. I,; ' dPI . ,' 7,' , i3l s __

Specification Control Ml1

{ I f b-gf This system collects daily specification changes and new f ~ .s , k

                                                                       ~

inform 1 tion from design agencies, and controls the updating I cf specification files and the reporting of these specifications in use back to the design agencies. .. g#.9 I

                                                     '                                                                                   . ,                   ~,',I j',, l                :
                                                                                                                                                                        ~-                 '

Cartification . , b {, , A This system maintains records' on parts that are certified ' 60 'q' :'- ' I hD,. W

                                                                                                                                /

O

                                                                                                                                                                            %^f            *       '

through Production Control, per Specification Control, U " 'S through direct inspection or sampling in Quality Control, and j brings together the records necessary to assure that the , i product has been produced according to specifications. Y-12 data processisis erstems assist in contronW er smonitorW a wide vertesy of . prod =ction and support oPerstions. . Ouality Control This rel:tes to the system that samples certain products and  ! provides statistical analysis for certifying all parts of that ,; j type. .

                                                                                                                                                                                     !l       t SS MIterial Accounting                                                                                                                                                          I j
                                                                               # " 8*I'4                                                                                                     '

A system that provides an inventory control for strategic matsrills. The system that relates to radiation monitori-q, film badge analysis, and  ! personnel health checks. ,

                                                                                                                                                                                           'l Maintenance The system for priority scheduling and time reporting of           Engineering maintenance work orders and personnel.                             This system schedules and time reports engineering projects and personnel.

i ________u_.

                                                                                                                                                                                                                        ~
                   .                                        .                                                                          17 9.'                                  a           &

crit.icality studies , QQ 7( . d .f , u-Critical experirpents with simple geometries of fissile yf .1I , 3 materials are important to an understanding of the neutron / +'V ' ** processes occurring in a neutron chain reacting system an ** the time scale of specific events. Such data are also useful as F benchmarks against which nuclear data and computationil -

                                                                                                                                                                         ~

j methods are chacked. In additioni these data contribute Ao .; , kl.f Y the knowledge of subcriticality and are useful in developing techniques tio be used in the measurement of subcriticality in

                                                                                                                                                                                                                 .'W' 4:

l l Plant storag's configurations and quantitles of fissile materials .:,-!4 .; l l that must be handled. i. . A.  ;!:

..j{% g]t ' i." Y J . . l p ,, ' i. ' 3. '; ;  ;

• f t..

Critical epperiments of reactor design concepts are sigrhficant N'; -  ! D ' Q N *i ,qd; I ;N

                                                                                                                                                               ~

economically as well as for their data on the behavior of j

                                                                                                                                                                                                                                              'q nuclear parameters In' reactor environments. Measuregnent of
                                                                                                                                'g   "
                                                                                                                                                                      .,. d. I b, ' . . '} h design Wometers early in the history of a program. Il guide and in 'uonce the ultimate reactor. configuration. .
                                                                                                                                         .f ..
                                                                                                                                                 }                e;                 ' 3 Afb [M
                                                                                                                                                                                           .ktI.N w . i .0 -q
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                           " ;. p :.;..

hk Criti 2 experiments fd I,aclear criticality safe purposes

                    ,                                                                                          pkj              ' '; a              .,                           ([}+                     ,.

meapre the mass of fissile gnatorial required,f criticality and,the,influenos'of diluents, geometry, type a , degree of g

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cO [g ,!.,;g'  ;.4t.. , ; y,.. ' rt 3 7.

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1 netjtrpn reflection, and peutron interaction among subcritical  :.

                                                                                                                                         .!g                           .

. y .. h' r , ;' "',,

cornponents.. Ini special programs, the actualgriticality or subcriticality of Plant process equipment may determined. h 4, f., m: 11- - g3'i ,ft .. . Q gti gh*'.dd t. All arlticality data generated in the three areas re potentially l' hy ' N - Ipf y 4g,. ,

                                                                                                                                                                         - ,}gab                        j , $i /                               -;3 useful in nuclear criticality safety programs. :                                  ' .' T     ' ;;ik:.!'

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                                                                                                                                                                         . q Ny . 4 ' ;h ' .                   .,                       !lt        -
                                                                                                                                                 ?.         .
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F, f 2 : --- - d l placement of uranium discs.*T.' Above right, a segmented enriched uranium sphere used in remote-controlled criticality tests. Center, a test involving Bottom, an external vi (g i I f q

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                                                                                                                                                                                                        ~

y I Y 12 Ottical Experiments Facility. -- , n i E _ 2=

                                                                                          ._       ._                           ._ % 2

9 [

-        radiation safety and industrial hygiene The Radiation Safety and Industrial Hygiene                                                              'y                      7[ ,, . g Ny-Department provides technical and monitoring                                                                   ; j t- 4 ry
                                                                                                                                                     ,                                              g @*

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         ,                     support in effecting the Plant policy to protect
                                                                                                                                    .'jbk!N0lilfl         j;] .

C , 3 : ,. . [ p personnel from exposure to ionizing radiation, [ ' ,' ., , ,3

• k'* {0 ;,2lF ,

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radioactive materials, industrial toxicants, or any 5 . ? {,.

                                                                                                                           .         . ~t                     !}:' l..                            ,

L other environmental factor which may cause sickness, i },hj,;. i bi *

                                                                                                                                                                                          . j [ " l.0 ll                              impair health and well being, or cause inefficiency                                    Y'$ $IM
                                                                                                                                     @(jlf.? '
                                                                                                                                                  '               ey .

4 * (i , among Plant workers. It is also intended that the y {,' ifg;. -

                                                                                                                                                                                                           ';                               G

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detrimental impact on the public at large and the ' I surrounding environs be kept as low as practicable. _____@_ __

                                                                                                                                                                                                                                           ~=~

Wgg Accordingly, ef forts are made to provide appropriate nn controls on liquid and gaseous effluents as well as *7 1  ! 'a solid wastes. Continuing monitoring programs are

                                                                                                                                          ~

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                                                                                                                                                                                      ,: g3
                                                                                                                                                                                                          !$hV                                    4 l

• maintained to provide the needed information to m -.-

                                                                                                                                             ~"            ~~

assure the detection of abnormal events and initiate . _ _~

• g _ _ _,

corrective measures as needed. Air monitoring stations in Y-12 use computer caras with a built-in filter. When removed, the card and filter are taken directly to a u keypunch machine equipped with a scintillation counter that prov'les g r.: g ,..,3. pl'y *' ,((,",'j.p; ;4 ']

• p an automated analysis of the sample. ,

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l1,f.j, ((' ')w. g, ., . The Plant's water effluent is detained in a storage pond to ,

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• p*.j

                                                                  ,h',g,{ '!-k ,Q ' .'              permit a controlled reicase to                                        o-                               UN                                      j h.[~.              '. ,l
                                                  *>                                                the natural environment. An                                     'kY            %7                      Y  "'_ f           d            ,I

( '{.

• sutomatic monitoring system s' [ i y

t, *.4 g . , , I M sacertains that the water re-h

                       --         ' N*,l,l                ;

g-icased is not harmful to the j 1, j

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h.! h ;j c:t (;

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                                           ~

p- w cg. a K Eng,neer;ing w, ' .:

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           . '.l k Y-12 Engineering is pwt of a consolidated Y-12 and Oak
                                                                                                                                                                                                                                                                . lYI                 .[                                     t ff.Q Q
                                                                                                                                                                                                                               , M;
                          ~ flidge Gaseous Diffusion. Plant engineering organization                                                   ,           s
                          . which serves both plants. Y-12', Engineering supports                                                                  73                           .
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                                                                                                                                                                                                                                                                                                         ,4 -

• j i .. production,' development, and the various support activities

              ,,    I,                                                                                                                  '
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                               -l the , Plant. ;                                                                                                                                                                   s                          ;: .
                                                                                                                                                                                                                                                                                                              .'* .l. *s {

t T The'several hundred engineers in the Organization are ,,, g' $ i cngaged in design disciplines of mechanical, instrument and I ~ "

                                                                                                                                                                                         '-     'T           '                                t                                 ~ "j g Q
      ' l ' I slectrical, civil and architectural, and environmental controi
                                                                                                                                                                                                        ' %wN.3+
                                                                                                                                                                                                        <c                     qD     .\                            -                  "                       .
                                                                                                                                                                                                                                                                                                                                'q(4 engineering, and engineering mechanics. The Organization is , F                                                                            -

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               .a                                                                                                                                                                                                                                                     N                                     ,

j0,%j: distinguished by its versatility of skills and disciplines with -).. ,

                                                                                                                                                                                                                                                                            ,.                             S'j                     ';'        .I j tasks ranging from the design of intricate instruments to the ~/.. -

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                                                                                                                                                                                                                                             'T -.. .

N g"d{M[%- (.t ,, fQdesign of multi-million dollar facilities that include complex & I '

                                                                                                                                                                                                                                                                                                                             -,'i l                   '

4I g process systems and building structures J I g, ; .'with,

                                                                                                                     ,. , i specialized,'/*.N

(; g. anyir,onmental controls.,;.' . . .% , n 4.,

                                                                                                                                                                                                                                             ' M 't;g .                                             ,                                       ,

jor'funct include's in ical design of ling,' f } d. p

                    ; 'chardware, and fixtures employed in production fabrication as .f, ', .

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                                                                                                                                                                                                                                                                                                                                 -e ii p' ,well . as' engineering support forc operating automaticallyS'                                                                                   .1-
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                ,f'[crd      programmed                               machine'                     tools.         Computer software'Is                                designed
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l'4 Maintenance; Division la responsible for the ilpkeep of 300 buildings,500 acres of grou'nds, and ' ver I

                                                                                                                                                                                                                      \,,'             (..   "

4

                                            ~

vehicles / as well' as equiprnent that ranges from the simple to the highly sophisticated. Mpdern ,( ~, ., 6 ment techniques such as computerized management information systems, a standard data est , at ing man . 'i h p.' , , , end k~ meesurement program, and: supervisory and craft training programs are employed to achieve . .} ;, ,, h optimu ', ' - '

p,91 .Alg' i

_ ,t,3 . , , . economy

                        " M W,. and efficiency. i'i :%q 3

T' ";' .;?4- . ( rd ,,p: y The Divisi is composed of five departments and a staff' group'. Work'crmtrol centers are responsible for

                                                                                                                                                                                                                - i j h'*                                   r        ,

the maintes (of geographical: areas. Two of tho' departments hwe central shops and also serve the j . 41 general plant .' The staff group provides systems analysis, training, lubrication engine ng, costs and , .' %

                                                                                                                                                                                                                      ?

budgets, and -work piensqrement for the Diviolon, and serves es (:er t manager of Plant iicles. .. 'p i

                                     ,9'r,$,r6:g.f'!.I'%4!'l0.20. ' , j l H 2 t. . 'i C;1 i > 2.4'.                                .
                                                                                                                                                                  +                                                              ik k-[,

The work force ir ddes bnskilled arYsomiskilled,' workers'and highl[ skilled M

                                                                                                                                                                                                                    -        *                  O} , '

craftsmen (electric instrument'cmechanics,, pipefitters,1 carpenters, and ,1.f.j [l'c welders). This work provides' maintenance support' to other Plant Jrc' i divisions and to the O f ftidge National Laborsq facilities located withiri,iH.N . the Y-12 area. , E Quality of work ranges securacies of precision mea

                                                          ?nopnel tolerances 'to'lighly                       l          demanding[

tS syysg g spontain delicety electroniplnstrumentet .

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                                                                                                                             ;                                                                                                       ,.1 3 ','   J i'.'

Repairing complex instrumentation is an irnportant ', ,.3 , I responsibility or Maintenance personnel Above right, a leak detector is inspected ror repairs. Be-(* '

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p.r low right, the DCX-2, one or several tarse Oak Rktge National laboratory thermonuclear research , l ,

                                                                                                                                                                                                    ,y                                                      *T. 4.{ '( i      s ;
                                                                                     } yk3-[                                                                                 '
                                                                                                                                                                                                    't machines. is maintained by Y 12 personnel.                                                                  ;     ,

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g.y 4g 1 jstandards laboratory 1 .. . t . c (' An additional important responsibility for the Maintenance Division is the[' g b 4;d E

• _U i operation of the Physical and Electrical Standards Laboratory, whichg .;

establishes traceability of the various modes of measurement encountered in - y' - g_ 7 I: p ""

                                                                                                                                                                                                                   ,                              ]

j process instrumentation to the National Bureau of Standards. 8 t[:

                                                                                                                                                                                                            .E

'j

                                                                                                        ..                 jE                     ,NsM                   '
                                                                                                                                                                                             #32$D.7                        d          I, - }.' ' ,*

2 This responsibility includes measurements on electrical units, mass,

   )Jt:mperature, pressure, photometry, frequency, time, environment, and aM ;
                                                                                                                         ,h.-          * *.
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I , 5 :- i l '

                                                                                                                                                                                                                                 ,,j Qf ,;; ) ij i

v riety of measurement combinations such as acceleration, vacuum, leak - T "Id rate, and flow. 7 8 - y .' ,.ti t b',

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                                                                                                                                                                                                              .,    :            :.). I    3,7 ' .i :           t I  This Laboratory is situated in an area designed for both the degree of Q                                         T ' ., ~

i

                                                                                                                                                                                                                       .j;.,;}[                                      ,

h[ , U, ~ E;{ isolation necessary for this type of work and with environmental controlh . .$ . . ,,[li:l: h.'. {edequate for the measurements required. q ,~ F;.

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I Shift Superintendents and Utiities The Shift Superintendents and Utilities Division comprises a group of departments primarily concerned with providing Plant protection, security, and utilities services. ,] e Plant Shift Superintendents coordinate the activities of the Plant i; the absence of Plant management. The Emergency Control Center is  !

                                                                                                                                                                                                                   !]

the headquarters for the Plant Shift Superintendent on duty. He is the Plant Emergency Director in any emergency situation that may develop.  : il l q

                                                                                                                                                                                                                   ! J 1

The Security Department implements the requirements of the Atomic l?.y,]U T."T "" 'I l' ' 4.? " ""S " *'~~ *7 rr Energy Commission's Security Manual. This department also handles the badging and clearance of personnel, processes Personnel Security ] gj$$$i ,.M h,j. ,. , .q r;F. g H Questionnaires, and conducts in-plant security audits. [g , . ,' y g ,i g. gg -g}. :mf7Tp.? , j w-i

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                                                                                                                       'f:
                                                                                                                                        %              DM;y*s: -riWMt.

The Guard Department provides for the physical security of the Plant. g i

                                                                                                                                                     . yc ', [T; ," Owpt                                       .g pINv @ IF                    W; g' The Fire Protection Engineering Department has the responsibility to                              69              ~l  . 8 ' *'" **T.

7 re 'E * ,t .- coordinate the design, construction, and acceptance of fire protection i - M* mb d. . systems and to inspect and test these systems to assure their reliability. l( y. .

                                                                                                                                                                                                                ]

Fire Department personnel operate the specialized emergency fire-fighting ~

                                                                                                                             ;.                                                                                        3 equipment and inspect and test the fire protection systems.                                                      L                                                                Et'                           -

, 'aM!)g. .$. I I The Utilities Administration Department operates all utilities equipment in , D ' , . +;, ; ~ I- q , the Plant with the exception of the electrical distribution system. They , g,;l , ', '. . ,7, , , q provide such services as heating, air conditioning and ventilation, water, and i ', . ; i, , 4 P . i , . j . j, ,

                                                                                                                                                                             .e      ,

compressed gases. -

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                                                                                                                                                                                        . 1      'J' Finnt Shirt Superintendents control room.

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gr\ . 4 i The Y-12 Plant Administrative Division consists of four separate divmons 'l 4 whose contributions are, with some exceptions, of a managerial and . . 7 administrative nature rather than technical.  :;  ; , j b n. - hl } The Accounting and Budgeting Division is responsible for the accounting of gy . i '!  ; , 1i j hundreds of thousands of major inventory items used within the Plant, n.d _.

;      assisting Plant divisions in budgeting for future needs, and accounting for the      4                                                i       .,

expenditure of Plant funds. @ , j 1 i . ; ! The Classification and Information Division is responsible for identifying .

                                                                                                                                             "-                                     !r
                                                                                                                                                                            )

those areas of information generated at Y-12 which require protection for reasons of national security and providing the necessary editorial, h i [ composition, graphic arts, or audio-visual services required to facilitate the I publication of significant technical information through printed documents j or visual presentations. The Division also operates a Machining and Gaging ' a information Center for the AEC. j The Industrial Relations Division has many diverse responsibilities relative to

                                                                                                           .} }

the general health, safety, morale, and training of employees. These . g , .l-responsibilities include the operation of a Medical Services Department ' ; T' . ; ' - staffed with physicians and nurses equipped to conduct many routine . , [.' p ,a, y, examinations and to handle most types of emergency cases. . z;c f h ~ This Division provides for a continual evaluation and promotion of safety I!:.S . l procedures ar.4 training; interviewing, selecting, and orienting new T 1 employees; admiaistrating employee benefits, including counseling to l _ . %1 - ' retirees; coordinating a recreation program; operating a Plant cafeteria; and - maintaining communications between management and the several laber bargainmg units. 5 I g p The Materials and Services Division provides miscellaneous services including rNM- 3 the shipping, receiving, and storing of thousands of items; operating a mail service; maintaining official Plant records; timekeeping; reproduction, and h, ~',N. iMM*. - . cashier and travel assistance. S

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d u l ba en . r aiac v r n i n l a v o ncigtemm a t i i . e s m r p Do" r umfor yu c ors t e a e s r d p i t ge a r a dxi i n l gdr o nf o oo e cm b e p E* ne kd o nol lar P P NT ciame uh s nad  : o nc hcyr s tam a n ma o c n s r gs eis i f d t e t eb u o isf s s f a ,tnce 2 o 'n n. f"e 1 i rl a a n d t at s e en

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s e n a a e s d n s. et in s ni e ct i r pr l e prairs a cuf e e a pi e i d o up a d goomt e opm nf n o be i s es t a ae eav i t a h p ni co r r qx pee te rp i i p r HCroogtyos s m a nl s egn

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l r ep eo t l g is d a i Otsid ghr e yn ncu odi e abl t o e st e i niw t s r gi p r p i s ewer s ep e vh ot heid l c Wfa na ub ri u he d TIn CE" r ant e es ci e ph d at lpe h T e Dnmr P w d 1 2 3 i n

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i . Since 1966, Y-12 has participated in a demonstration *, I - e N

  ' ? [ ;-<                                                                                                  "

industrial training program in cooperation with the Oak * ' g *

                                                                                                                                                               ?, '

h h' .jr Ridge Associated Universities and The University of

     ,. l          f'                                                                                      4- ,,

Tennessee to train unemployed and underemployed persons

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     , ' E , .[ in several occupational fields, and to update the training of w

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                                                                                                                                                                                                                                                 ,j
                                                                                                                                                       ,                                                                                         g technical and vocational teachers.                                                                                                                                                                                     ,

y q The program has been expanded in recent years to include

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                             .1 persons sponsored by US Atomic Energy Commission e

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      *1                 4 contractors located in other states and selected students from                                                                                    ' ]                                   .
 ' ' { (U,1;                           the Oak Ridge High School. Approximately 200 students are u

8N g enrolled in the programs at any given time. A typical student ~ i

                                                                                                                                                                                                                                   ~

attends the TAT school for a period of six to nine months g ', and receives daily classwork and shop training in one of the following career ficids: machining, draf ting, physical testing, G.]T1 welding, electronics, and mechanical operations. Thus far, E,'! : ".h over 2,000 trainees have successfully completed the training

             .b.E c1                  provided by the program and have been able to obtain jobs           ,
                                                                                                                                                                                                                         ,(yj ., y'-=<-
'. .t'hj y.l k that pay considerably higher wages than they could have                                                         ,j ,q .

? . d obtained before the training. A number.of TAT graduates M, .A. 2

                                                                                                                               '.              -               I g                                                      -

QN.$ have been employed by Y-12 and are performing very 4 u- - l , v a ceptably. .{ .f , [ ~{ 1 p , l h ' The training facilities also are used by The University of h Tennessee and Roane State Community College to conduct P < ' w 2,)p

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credit courses in the afternoon and evening. Approximately

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                    .l                100 persons are enrolled in the college-level courses at any                                                  '
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given time. N I . - S k:.

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h, !9 'r. .j,. .ignyv.l. . .- , I .,..y u Above. rnechanial operation students adjust pipes; below, a machining student j hh e b .'; , ..(.'

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                 .            l operates a vertkat turret tathe.                                                                                  _

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l I l f i: This report was propered as en account of work sponsored by the United E States Government. Neither the United States nor the United States Atomic ' Energy Commission, nor any of their employees, nor any of their contractors, f; subcontractors, or their employees, makes any warranty, express or implied, or

• essumes any logel liability or responsibility for the accuracy, complete <tess or usefulness of any information, apparatus, product or process disclosed, or ..

represents that its use would not infringe privately owned rights.

                                                                                                                                 -      i f

9 l g Reference to e company or product nome does not imply ' approval or recommendation of the product try Union Corbide Corporation or the U.S. Atomic Energy Commission to the exclusion of others that may meet specWicetions. , e

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      ,'                               INFORMATIO'N CONTR01. FORM ~

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no isa nee seen e asy re.nese. One @ rm ter.eann _Y_-!'l-4 ' h ="a d 3 = a= = m eveerne other public tr. formation releans. 8E]utiff3 aCT Cao aveD S'lf e+ t JT 'h Deslaseiassaan's Oiner assnes inee eeneree W der aseeeee ] Desumens Peeneseen * ,

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s. 3,seass gpayne' ge,sen,n To be selectivelv dissegineted bv UCC'fD and UttAC versonnel in conjunczion with recruiting and public information programs.

                  !.                                                                .s peo w u ..o ari. g st N0f ts seeme ,e to.h.*eed lete mes.e Ze.e.eee enen eemetee ee ed wereel oeer s l                   .

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JANUARY-DYCEMBER 1960 123 Co. at, Hanford. Proposals from private industry were received dur- c at Oak Ridge, aperated to pro- ing the summer in response to an invitation for proposals to manu. s development facture, in private facilities, the uranium metal billets for the co. , to escure con- extrusion process. The prices quoted by private concerns exceeded ~ by a substantial margin the costs of producing these billets in Gov-mprovim:nt of *4 fiird production ernment facilities. Consequently the Commission decided to pro- 3

          -                                      duce the fuel billets in Government facilities.

A study on the economic feasibility of converting the NPR for the j recovery of electric power was mcde by the Federal Power Commis-sion (FPC); its report was published during February 1000.' Ar-rangements have been made for additional studies, including an up. f terials proces-dating by FPC of its earlier report, to be available in 1961. (d m Juns1958. oolition cnd site o Arch Wreck- Gas Centrifuge Studies expected to be

• t am owned by The Commission has recently increased its effort on development iical Works. of the gas centrifuge process of isotope separation to an expected f ths build,mgs total of approximately $2 to $3 million per year. The development m suse, such as the program will continue to be classified. (See Appendix 20 for AEC '

ewer plant and statement on gas centrifuges.) f tracks, es well The expanded program includes three major areas . . olition contract uisition value, Continuation of basic research which has been underway at the  : University of Virginia, Charlottesville, Va. i-er Government ment, at acqui-Experimental operation of small groups of machines incorporating l uranium indus-ensees made it presently available technology. This work is being performed for

> sale.                                                the Con. mission by Union Carbide Nuclear Corp. at Oak Ridge,                                              .

Tenn. l Development of advanced gas centrifuge models. Interested private companies with the best capabilities for contributing to , teactor (NPR) g 1960. As of the program will be invited to submit proposals to perform develop- g~ i complete, con. ment work on the advanced machine under contract for the l percent of the Commission. . . mr 1,1000,the sted to remain Military Application l S',-500. These f et an additional Product. ion of nuclear weapons by the Commission contmued durm.g 1960 as authorized by the President. The production effort included wanium nei, $n and fuel ele- ..Resetor Power Plant Economic Fe.stbutty StudT" TRD-5762. Price $2.50. .vallable i trom cince or Technic.i serrie... c.s. Department or commerce, ws.ntacton 25. o.c. $en:ral Electric y.

                                                                                                                                                        ,,e 2,r.      yy                ..7.-              -- o ),
                                                                      . s-ee; *-
                                                                                             . ., 3 - - - 7
                                                                                             ' a ["I .,        *          -

7 g ,,3 - f.3-

• r. ** Ps * . . ,.=. g. t z.1,- 8 (*gn

g i 5" 4m ,J,z,

                                                                                                           ,           .o                                    ,

JJ 4 ='- . g i M 7f i '

'h j .f -QiQ. __ g;*

L 1.(g.-gmmQ. .

                                                                                ~Q  ~

_\ 124 MAJOR ACTIVrr1ES meeting new weapon system capabilities, modernization of older and northwest of th less efficient. designs in stockpile, and a retirement program for obso- , ballistic chara< lescent weapons. _ dropped from a The Commission's program of weapons research and development i Computer fc has consisted during 1000 essentially of laboratory study and analysis systems are regt of data obtained on the 1958 Hardtack and earlier nuclear test series I addition,there i with a large portion of the effort being devoted to translating these , fields of researc results into operational weapons to meet specific Department of De- t in research on si fense requirements. These efforts have been fruitful and defense welear propuls needs for numerous weapons of various weights and yields have been met. Further intensive research and refinements by the United States nuclear weapons organizations, even without tests, can continue to Exchanges 01 produce some design improvements. However, without nuclent test- other nations f ing, major advances in nuclear weapons design do not appear possible. , Report to Con: States-United siderably broat Test Facilities classified infor: between scienti. The Eniwetok Proving Ground and its facilities were maintained The United on a stand-b'y basis until June 30,1960, when the facilities were made Australia, Can: available to the Department of Defense forits Pacific 3 fissile Range. The Netherlan. The Proving Ground will remain available for Commission activities, lantic Treat 'v 0 if needed. Weapons test facilities at the Nevada Test Site have been maintained on a stand by readiness state. l We: I Weapons Facilities Work was initiated on the construction of a $2 million plant for treatment of chemically and radiochemically contaminated liquid The United 8 wastes generated by the metallurgical, chemical, biological and cryo- continued in E when negotiat genic laboratories at Los Alamos Scientific Laboratory, Los Alamos, f N. 3fex. Construction also began on a $3 million special metal fabri- and the Unior cation plant at Oak Ridge, Tenn. to meet weapons production require. J treaty for the I ments. To put in p I Transfer of ballistic drop test operations from the Salton Sea Test suspension of Base, Calif. to Tonopah Test Range, Nev. began during 1000 and is history of the , czpected to be completed during 1001 at which timo the Salton Sea Conference of l Base will be placed on a standby basis. The Tonopah Test Range is sentatives of ' Soviet Union, to August 21 l l

• See r. cC.

l g g ., -- -

                                                                           .,7-j-

• 6

                       ^

                                               , . r[a,      _

[*A A __

                                                                                            -         f- A JANUARY-DECEMBER 1960                     125

) of older r.nd northwest of the Navada Test Site and is used for determining the ham for obso- ballistic characteristics of. inert (non nuclear) weapons shapes dropped from ain. raft and for firing high altitude research rockets. dsvelopment Computer facilities are being expanded. Additional computing 3 t.nd analysis systems are required to solve complex weapons research problems. In nr test series addition, there are problems which require computer solutions in other % sitting these fields of research being carried on by those laboratories participating , bnent of De- in research on such programs as controlled thermonuclear reaction and ' end defense nuclear propulsion. ds have been blutualDefense Agreements continus to Exchanges of information under Agnements for Cooperation with nuclear test- other nations for mutual defense purposes, reported in the Annual " y ar possible. Report to Congress for 1950,* continued during 1960. The United States-United Kingdom Agreement for Cooperation, which is con-siderably broader than other agreements, involves the exchange of classified information on nuclear weapons and the exchange of visits between scientists of the two countries. ' maintained The United States has mutual defense agreements in effect with w m made , ,

 ,                          Australia, Canada, France, the Federal Republic of Germany, Greece,                         O issde Range.

pon activities, The Netherlands, Turkey, the United Kingdom, and the North At- 4 lantic Treaty Organization (NATO). f te have been r Weapons Test Negotiations and i Related Research I pn plant for e e pated liquid .al and cryo-The United States voluntary suspension of nuclear weapons tests continued in 1960. This suspension dates back to October 31, loss, g lLos Alamos. when negotiations between the United States, the United Kingdom l metal fabri. and the Union of Soviet Socialist Republics began at Geneva on a $ ion require- tnaty for the discontinuance of nuclear weapons testing. )h 4 eon Sea Test To put in perspective the United States position on its voluntary suspension of nuclear weapons tests it is necessary to review the j L 1960 and is history of the test cessation negotiations beginning with the 105S 4 t ) Salton Sea est Range is Conference of Experts at Geneva. This group, comprising repre-sentatives of the United States, United Kingdom, France, Canada, g Soviet Union, Poland, Czechoslovakia and Rumania, met from July 1 to August 21 and concluded that it was technically feasible, within i. ^

• See p. 66.

                                                                                                                 %           e
                                                                                                                             's

p. . '

i T.. 1-

                       ~

y . j .7 9gg4; ; J.[ y J ]3h. .rc

                         . 2;m- %g :

a

     ,7                        .pw:
                                            ..                 ~.                  .
                                                                           .s. 4.u.a. e.
                                                                                 <                               - 8   m. -m

• M 4

w Q h b_.'a .auy p ' md rih h.Lr.U.1 - 93 0$19

           .                            ..                                                                                                                                                                                                             4
                 ~

cLurron couarsa utws .1E 2 21965 Picss, famWes see ared . Y-12 plant opened for tour c for first tirne in its history llY 110ltACE V. WELf4 Jit. **Y *)

• 1 Fur the first finie in its 22 year T

                                                                                                                                                                                                       '                ' WJ sC.

instory. an arcs of the huge 4.5 mil- ** f.b I '- '

                                                                                                                                                                                                                                           .I lieu squarc feet Y 12 ilant sa                           ,   4 g                              f-                                '
                                                                                  / a-oprutd to tf.c ublic ast week.                              A                     'g            '

4' /: . . , ' , . WI.dc families o em # . -! [' \  ;~ -,"[ ' '... . ' cibers uhu wwk in Oakilayecs a n d  ; DWe vlm- ' cd the arcs Saturday and Simday, nen mclia repnesentathes ucre e

                                                                                                                                                                                   '..                 .~

• M 3. . ; M/,.~ d;ff
• h]

jh Afven a special leur en F r!d a y - - .N 3'$o' 4- .. c . .- cecailui fur the huuse' was the opening of a new laimratory fael!ty, stuch added

                                                      **v p c n
                                                                              ,2 T
                                                                                                                                             .[   .

I - 4

                                                                                                      .;          .e                                                        f                                       ..             -

p.000 srparc feet to the devciop. 1. $A L '^'.. I

                                                                                                                     .                                  e (7                        L .c                                           ,*                        '
                                                                                                                                                                                                                                   ;;;,' 2 picat drilmica and will provide                                                                                                                                                                          ,

' room for m:ny of Lt.e departrneuts to spicad out a li111e. if - r ',...,'.p. x' A tra

                                                                                                                                                      *U,I           .
                                                                                                                                                                       '     ..N - 

i' . . , . ". n..

                                                                                                                                                                                                                                                  - il

! Vndors to the plaat .5 'tD 5 'j .

                                                                                                                                                                                       *                  #i u  O ' M

f '* uur!d's farsc>t and ost m.versatile one of the 4 T.Y, j / '~ W RH machlac shops were ovenheimei l

                                                                                                   . C ...                             3*'
                                                                                                                                      #*            3  ,..                                   4-
                                                                                                                                                                                                         't                            ..

with the acope ,of the activity. Whi?c '

                                                                                                  '@'                                           3*.$                                    ?                                            '

isormal incial sorkhtg facilities d. dent ulth frun. steel, brass and g p"g r'

                                                                                                                                                                                  . 4;j   t' di '.i t

I 00wr readily recognited mela!s -

                                                                                                                                                                                                                     ?.IT the Y12 Pl.1nt is gested to h ndle 4,.j'                   .    .                                 EQ*' 4
      %         such mairr!als as uranium, thort.                         f .,, -                                                                                                               /

um. beryllium tungsten and many

                                                                                                                 !,th,                     p< '                                        ,
                                                                                                                                                                                                                                  ;p cthers relatively unknown tu most                                                                                                                                                  '
                                                                                                      ,' y.%r'       "'                           '- .           '

preiph> out>lde of cct!cgc or high school lalairatories. l c

                                                                                                                 ";G c                                                                                                h?                 t Fascinating as the stran*e met.                                                                '.

i

                                                                                                                                                                                                                       'v.37
                                                                                                                                                                                                                          'A f                   '

als orc. !! Mas still a g'old bar val- i ,. dEM med s1 815.000 that caught most I

                                                                                                                                                                                                              //Et W "4 cyrs - 1,ut when told that a bit of                                                      ";'

tuimium enly about tulet as large '

                                                                                                                                                                                                                    Ct 2

was valued at . gr.5.000. ' you *W* t '1 some idea ab'out the placc. se **Ct d

                                                                                                                                                                 .                                                                      -l Ruht. 'Intidenta14. was fastened g, ' ' *..  ,                                                                            d.       e ' D.y.        *
                                                                                                                                                                                                                           ' 93' doun whf!c the uranlum was het! . ,.-                                            *           ..
                                                                                                                                                                                     * ?,Y IS.                       . . .            .I     '

i What would you do with it, it you .P had it, we wondered. f' , M.It :tF ' j'.e. %y Especlany exelting were the ul. ' ~

                                                                                                                                                                                                            ?              Mr.H
                                                                           ,"%.                                              7"4                                                              .Q Ag trapretistun an=40 cal and inspec-                              *                                                                                                                                 -F9.-ji>,

tion esimbilitica cf the Y 12 plant. X ray machines that can "s c e new s:r g ' p* Q.. -'*- J t

                                                                                                                                                                                       'gs"g%p&.g
                                                                                                                                                                                              -I
                                                                                                                                                                                                                .N:-h throust."           loches of solid metsi TV pictor of an x ray exammatlo"a                       FAMIf3 DAY PREPARATIONS-R. F. Hibbs superin .

t n bit at an u$ fendent of the Y-12 plant. holds one (if the m,etals dis i white the escapn'ent uheel turned played the plant. for the Family Days hcId Saturday an( Sunda en tt distl ay beIly l'tems'to.'the m!!fionth of an inch in

            ,ere         mouno ts.i couw mca,m .a.iyan,w tu - orn.a.

Then the encloilag coil was heated

                                                 **-a ' y ,, . 4 I

M and soon the fleetm2 metal turned

                                                              -                                                       r                                             "
                                   .                                    .           r                              i        '.          ;.

red. then thi matten metal f a a t. C

                                                                                                                                 .                                                                  c.! in the air until the cQMatcr was                       D ready to re:Me it Int; a ecnt:Iner.

I

          '          -[. @'                             p                                                 .
                                                                                                                       ~~'

W'. litto sh!ch it " poured ilw;f." g As usual a (my electiie !I g h t

              " .f1 * $, .s. .. .                     *f* Y     ' 79'.g, se,;,ph3QTp; es c g, i                                                                      - . . .

bulb the worlds smaWst" - U

                                                                                                                                                                                                                                                          )M T h y * '. ?                                                 R. . . +,               Lj #,,
                                                        ,' [, ) P ' "~ g'                                         MN',*f t. t c/:.9,, .d.        "
                                                                                                                                                               - . <q.q W.

F

           '.,*l -                                                     ,f                                                                                                                          tt Aswa,        labelcJ.

flash cncau;thf ushed a button, rnost the tiny c ,es c> Q es

c. .

                                     . .k..)

d,,

                                                                     '%                            c p-                        9*M                                           you pd bulk wou.                     just as bi;t J.b    g*' A        W ..'SN'                       wx ,..,.,,;,,,%.h"tr=-,j y ,',Q 2.'. h~. . *r,
          , .. e                                   ..

do. Thrcugh a mieruseope, it vas ! 1 L- i " *' .d late to examloc cae cf the tiny a u ! b s with its unbcl.evabfy sma:1 i h..D g M C.* C'W. *j bjt of tung ten ulce cac!csed in the l t ',Q.g'h:.S. ";3 .- . tmy glass tubc. T.tc 1:ulb wn: sakl 2 e "t -

                                                                                                                                                                    ;*                            to be abou: as large t.s a hag Ash
           , fr.'g '                                  if.v(eg                                                                                        ~-

• i-) and maybc cs widc as t h e

                                     ...                          s.f                                                                            .                  .

line fiom a ball point pen! I I ) t' ". jj n I In the et.urse of the tuo Imur:,' e y - 4;%rf f,g#%p,5 b.,. c',8 'l C 1 ,, lhe group saw onla a fractien of the huge area -about one per cent of

         . 7;h@.j.,.                                                                                                     e                                                                        the 4,500p)0. square feet, vc were

w. .. .gh r,a i .

told. Into voeb a space. marc them'

                                                                                         /.                                        f h[0.# '*

• f. t Fq r. . 78 footbati fields could be fitted., thc'

{(.* v < Q:, '%. )[M.$ ,4 e tk- r[.J Y y-

                                                                                                                                                                    'A.                          Y-22 Bulic!b poir.ted out.                        I
              >     .d.i3- , ' .
                                            ,gr             .                                            ..

sy. J ,7/..? But in that time we did leara gv.d 4

                    . . . W]. ,.lr,',;                             ,

i something about isostatic prcises,

                                                                   . f. ***QMM I

U:~

                                                                                                                                  ,f-               Afg JET,jj,.3       ,&

of which the wor!Ws largest is at 1

                                          .S 'r. .                ,n,                                                                                               G Y 12 Iwe didn't see it. howeict.)

[J .

                                  '  ,   . i a ,W
                                       ..d l's.

e

                                              ' q' .

l,. .

                                                                  ,f,7 *;j')

e ,; 4 ; ( 4 3' These presses esett the same pres-sure from all directions at the sama time - not on the tcp and bottom I .[.Y'.* %[*. . 9.,, ,

                                                      ~

j,\>.*'% h...f[ as mcst presses. In them meist

                                                                                                                                                           '.b,0. F g3.;I.
                                                                  . ,.j ,                c~.M. -Q  :

j;g,g...:, T. ' ,. I powders, are prcased into a sNid b /r l'j,..[* .'.8.,

e. vv. t".. t.M metal, or under great pressure heat

                                .                                 ,c -                                                                                       y:<
                                                      .g,
                .

• y. ) ;' s.M.,i ,,

4 s. .,K ,,. g- is app!jed and solid metal rew!!s.

            > - Q .* *, *.6 ;,g ,('*                                 ., k.
                                                                  *h,.,                          , ,j. .',g_'p%
                                                                                                 ~
                                                                                                                          ,b;g

[jh.  ?

                    .? .*lb/ 'Y .IS.Q
                                                                                                              ;lr.L ef And we saw the actual dalec
                                                                                          ,                                                             i                                       that made a trip into oute: space 45
                 ./,t                                                               ,;. S
                                                                                       . :. 4,bg3                                             .1;j$q:lXfa,                           Fe aboard Gemini 3 with binod samp.

d."f..,.T les to test irrcdiation, one of the 3 *$f,'Q);..gm'A /D, 6 v nf&/?1 ,'i.;e.x s. :3 few biologleal experiments that se.

            "FitOM                         IDEAS                  TO REALITIES"-This                                                                                                            g(Woged, And ere y.12                    plunt               shows                        how the dcyleeexhibit                                 used at              in the t              Gemm, the                          e
                                                                                                                                                                                              .matic laser-Interometer calibraWr jercQif,-                  <

blood experiment was. developed from a basic idcu. Artt. aad an electronic compr.rator, eles tued in slmthtr tests were on display for the Fa mly ,pon.t ask us what they did. for D.iys program held last weekend. ,, - uhen it was esplaine:t we sti jdidn't know and we. hcpe we won,it In;t lef. ire the eyes la large numer- . need one in out a, hop. ris the results. And other ma- As a covelty, one of the fabr.ca-r!dnen en defie.'te thet the ext:m- tion machines was being uW tol sion af elect e:rs caused by .the turn out yo-yes! Tacse plastic e.ou. heat ficm n human hand cou!J be senirs reminded us that the Du.1-re:id initsutly. And these werc run can Company, for mcre than 30 of Ilp* mhic instruments! yeats 11.c worlis largest yo-yo la lhe Y it Ind! dings are amaz- makers. went into br.nkruptcy last 1 c facilities. . ucck. While tbc firm sursived the lf you here a need for a room hulahoop. It couldn't take the skate-wnh air free from impurities. Y12 board competition! }

   .             hn, it . After putting en speelal                                                                                                                                                Another machiric, operating from!

ch.thes and ectering over youf a perfarated tape sinular to the ore ohnen, you eguld enter a, room that controls the 1.inotype that 3:t ehere the air is 1.060 times purer the type for this artic:c. was busy ih:m that you breath' drilling holcs la plastic plates to And if you usnt moisture free clr ' tmtri ils roc!. loo!) there is a room, f arm the letters UCC - J or. to demotutrate the abibly of the ms-l(r m whleh the moistume has been chinc. rer.imed dorts to less than 10 per- Thc Y 12 plant was ballt 10 IN1 crni ens compared tu CJ to 80 in a and production <perations started e..rmal room.) Then, nearl>y a r e the nest year.'It was desigac4 o-if huge sensels with rult:cr arm en- innity to seperate uranium 235 I'V chisures in ubich the alt is entirc* 7.c e!cetromagnetic process, and il ly free from any 'molature, cost c!most ha f. a billian da!'cre. One of the most amaring of the The uranium-:35 separated a'. %12 i demonstiethens was the melting of g,13 the fisJicnabic material used ' mehd uhile la suspension in the air 43rdipNns. A small meud pieec in the Ecy."

                                                                                                                                                                                             "Little     wor!(awhich first atamic     bomb.)

va6 cet::sted ct.uot ene by one and a hatt inches Au:. 5. m3. was diciped into en c!cetrical coll

• cnct when the power sas applied.

                 ,tlic metal ficated frec Jn the,,,a!r.

O s2.osis - After the imd of the war, the ch'c! ltromngnclic 1aoIop e separa' ion [

                                                                                                                                                                                                                                                       'pr o ee s a wnt discontinued in fa.
                                                                                                                                                                                                                   .                      .             vor of the more economical gd@Js diffu>1 ors process eceducted at E.

IN. p,yy&I-

                                                                             ,,.                                                                                                                      ,, [ @                           ,4,              23. The many, many T4unds of s:1-f d             ,'e                                                       l               T" , Y. %.g. ,.t..                                                                                                                ver used for bus bars to conduct J
                   ' <gN           '
                                                                   /

J M,.l  :%' ptt. ' -) I3 P ',t.(T . .! the high voltue { cause copper was ciectricity not crai !3bWt ric. , 4 ., f I lb k f l- g 1,h .. iMir-. ,cp ,'1 . - f.' were retaracJ to Fcrt Kr:cx, Ky. l

                        <     i<

r q l. { r, y .-

                                                                                                                                * }b.p Jg'94 , K '-
                                                                                                                                                                               ' p.- S              'f.

• After the war, Y.1: was conve:t.

ed into a h!2hly sophisticatcJ ma.). ('

                                                     !              T'Q1**.),                                                                                                                           <

b II e . aj; < ufacturing and dere:opment enti., yf (lg 3 y,I o

                                                        "'                                    ]               j ;I                          '"~.*""r]i'.1O'to I              T? '                       i                    "1

(

                                                                                                                                                                                                                        ,4, f               necrina organ!4ation, util.ri.4 seme of t$c must advanced techr.i-
                                                                                                                                                                                                .p{

f.a\ 5, h

                                                                                                                       '                                                4..                         n.                                                   ques and facilities known. T h e t c
               '..1#) : r- 7
                                                 ,                                                       -       8                        -

q

                                                                                                                     '                                                                                                                      I are a proximatcly 4.500 people en.

Il g. 4.'l.f G ,[ e 4 - Q, t & Q- g f i i g l Idoyed there, including 500 scient. i b,h ' I !sts anr1 catineers, cod 1,2a ;c 3*. l3 500 skillcti craftsmea. mui. . E - 6 = I d'i . . ' l pt.*Q- g. Tne fir *1 producticrt respori:!.d. snaa.y ,

                                                                        *i

[g 5,

                                                                                                                                                                   >I'k"k;,.n'w~'f ,f ify of Y.12 !s in the field of r.v.:Or h

ij ... h .

• y ,gg,, weapons. to provide actual pans }

        . h .ge4t                                            .i                                                    ,
                                                                                                                                                                                                                    =                                  for bombs, and to serve as the fe.
            .y                                                        ,

ricat!co si;pport of the ucam. de. { r l ,.'  ; , .

                                                                                                                                                                                      . ,,yyp.
                                             ,, . .g                                                ,9                                                                 .
                                                                                                                                                                                                                                         ,,            sign laberatories at Los Alarwsl
               *.,b                                                                                                                                                                                    g ,. <                                          IJvermerc. Calif., and others.

n , j. 6,3 ,

                                                                                                                                                                                                .,h.,                                                     Then Y.12 supports the Oak nidge~

3ri q s f d. - P q h'atlonal Laboratory, onc of the na- 6 I,  ;% ,..,,,.. t

                                                                                                                            -                                        L; *
                                                                                                                                                                          ._                  Ni                                             .        Lion's !cading research centers.

f, ny . . ' There ore about 900 OItNL employ.

           }g ,).q        i      I s.

5 ,.,, f.

                                                                                                                              ~

f'

                                                                                                                                                              ~ [2 '. T ,1 tJ lp.                ocs lec:ted in Y.12. working in the biolo;'y. reactor, Ih e r m onudear (g.y                                                                                              c g.1 3                                                                                                                                                                 and azoto;cs dhisions.

j

• t k.'M '

u.e

                                         ;. ;' #,h(                      '
                                                                                  '4 .               i           L:y',[                                      ..'.'
                                                                                                                                                                                                ,                                                         A fourth minion of the Phnt Is g'6    l, l t ,af          -                  k J

4 I g -

                                                                                                                                                                    *s.-.                               .

the malatenance of a research and

                                                                                                                                                                                                                                                    'devc!cpment program in 1 support of I-)                                                  g;, .4o

(!p '

                                                                               .'     '8 I I                               (

3 l

                                                                                                                                                             / .i.
                                                                                                                                                                                                    $                                                the primary mission.
        ;      g'                          :

I L . W*,'r:.M .r , P r o b!cma involving chemis:ry. 5 . ,, k { 0- l, \ 4 *.* I [. engiacer'ng, metallurgy and 16brl-V 1 h & cation are eften solved there. No c.

                                                                                                                                                                                                                           . {,4
             !y           g                                                                                                                                                                                                        ts                worthy among the achicvemen;s p::)w,
                                         .- .                                  l                                                        f.?

• are the predne: ion of fuct c!ornents hy ',

                                                                                   '                                                   p',@d

7. for the nuelcar rocket program. .

8: 7.

                                                                                                                                                                                                  ,{! .

i.It h,% .

h. t,:' some lungs:en IDscris for Polaris 9c 1M 9

i. rockets, exotic mahrla!s itenu, bio-w,; j tj l

                                                                                                                                                                                      . ($. . j medical engineering a s s i s tance, 4
                                                                                                                                                           ,,i                                          ..
                                                                                                                                                                                                                      ,.,.                           and solu'. ion of spacc-tclated prob.'

I'p, '. .g; i 1 ' s, ,a-

                                                                                                                                                                                                                                  ],. .

b .H. tl 9 . . , l reca.

                                                                                                                                                                                                                      ;. 7- l-
                                                                                                              <.i*4. .[, 2l....T.'.~:: @.y Wh.f. ,.

mlgyp ii l'. . ' , .#

h. p .c. . ,

k ,.g. 3..,. 5

                                                                                                                                                          =.

y

                                                                                                                                                                    *,                                       b N l.                If                                                                                 N l~.Y
                                                                                                              ;7.: . .: ..)                                                                                          ,l.' -".           .
                                                                                            . .                                                   s                                        i s.: ..
                            ,.'. '~c         a ... %.4,2@w%.
                                                 ..                                   .4...

a: ..*. ,s. . .. o aAIAZEisd(. 9 . s. zg.. .s2

                                                                                                                                                                                            ,     l                                            ,                       .

OF PIPES--Shown abov'c is a. port!on of the large-scale facility for the recovery of enriched branium.used in work at the Y-12 plant. The inethod,.used above, solvent , extruction, was partial _ly' explained, during the Family Days program held, at the pla,nt 3.,.,.2.g'g.g. , O s assummer N h ,,

APPENDIX B

2.8 BACKGROUND

RADIOLOGICAL CHARACTERISTICS 2.8.1 GENERAL . The plant ,ite is located in the Oak Ridge area which has, over the past 30 years, served as the site for a variety of nuclear facilities. Loca-tion of the demonstration plant in the Oak Ridge area is not expected to contribute significantly to the environmental radioactivity levels. It is known that certain radionuclides have been intro @;ced into the envi-ronment (especially the river) by various sources listed below. There-fore, the objective of the preoperational characterization of the radio-logical environment is to provide baseline information useable to sepa-rate the effects of this plant, if any, fro $i those imposed by other sot.A.es including the sevetal Gak Ridge operations. The radionuclide population is made up of the natural radio-elements, fallout from nuclear weapons testing and releases from nearby nuclear facilities. n Programs for environmental monitoring have been in effect since initia-

             ' tion of operations in the Oak Ridge area. The Atomic Energy Commission (AEC) currently conducts the Oak Ridge Environmental Monitoring Program in the general area shown in Figure 2.8-1. The Oak Ridge Environmental Monitoring Program includes sampling and analysis of air, water and silt    .

from surface streams, fish and food products, flora and soil. This pro-gram makes use of nine perimeter air monitoring stations, eight ramote e air monitoring stations, five Clinch River sampling locations,- five surface stream sampling stations and eight milk sampling stations for monitoring radioactivity levels. Continuous samples are taken at all 17 air monitoring stations and gross alpha and beta determinations are made. Continuous proportional samples are taken at five water monitor-ing stations located along the Clinch River, White Oak Dam, Poplar Creek l and Bear Creek. Daily samples are taken at one station along the Clinch River and one station along Poplar Creek. Milk samples are ana-lyzed weekly at each of the eight Oak Ridge area stations and at one of fs F 2.8-1 l i l

Y four remotely located stations. Annual soil samples are taken near the perimeter air monitoring stations for plutonium and uranium analyses.

Mine samples measuring approximately eight centimeters in diameter by one - centimeter thick are collected within one square meter area. Uranium analyses are performed.on soil, pine needle and grass samples collected . quarterly at five points on a five-mile radius from the Oak Ridge Gaseous Diffusion Plant. The location of the sampling points, the data on the samples collected and the sampling periods provide an indication of the source of the radionuclide and the quantity released at the time the - release occurred. Remote stations are particularly important in assessing the contribution of atmospheric fallout to the radionuclide concentrations. The radiological characterization of the Oak Ridge environment presented herein uses data from the Oak Ridge Environmental Monitoring Program and state and national data reported by the EPA. A baseline monitoring program is being planned by TVA for the Clinch River Site which will be coordinated with the Oak Ridge Environmental Monitoring Program. Data from thermoluminescent dosimeters, which measure general radiation levels, will be part of this environmental monitoring program described in Section 6.0. 2.8.2 RADI0 ACTIVITY IN AIR, Atmospheric concentrations of certain radioactive materials are deter-mined under the Oak Ridge Environmental Monitoring Program by using . nine perimeter and eight remote monitoring stations.0,2) The locations of the perimeter stations are shown in Figure 2.8-2. Locations for HP-31 through HP-39 were selected to encircle the perimeter of the Oak Ridge area and provide data characterizing significant airborne releases from any of the facilities and any background sources. Eight remote stations provide samples which characterize the airborne particulates for the East Tennessee region and provide background data useful in C 2.8-2

PT SV7

   ~

C Two atmospheric nuclear explosions were reported by the Atomic Energy Commission in 1972.(4,5) The I-131 released by nuclear weapons tests

                                ~

is probably an important part of the I-131 levels observed for the sam-pie average shown in Table 2.8-4. - 2.8.3 RADI0 ACTIVITY IN THE AQUATIC ENVIRONMENT The Clinch River receives run off and discharg>ts from the Oak Ridge area through a group of surface creeks shown in Figure 2.8-6. Discharge from the White Oak Dam into the Clinch River occurs at Clinch River Mile (CRM) . 20.8. White Oak Creek has received much of the low level liquid radio-active waste produced in Oak Ridge National Laboratories operations. The Clinch River Site, located between CRM 15 and 18, is approximately two miles downstream of White Oak Creek outfall and is approximately 0.5 mile upstiream of a stream sampling station (C-3) located at CRM 14.5. Loca- ' tions of the stream monitoring stations are shown in Figure 2.8-6. A

       . continuous" proportional sample is collected at Whit.e Oak Dam (Station W-1) and is composited for monthly analysis. Continuous proportional samples are collected in the Clinch River at Melton Hili Dam (Station C-2),

approximately five miles upstream from the Site, at the Oak Ridge Gaseous Diffusion Plant water intake (Station C-3), at the outlet of New Hope Pond I on East Fork Poplar Creek (Station E-1) and on Bear Creek (Station B-1). Samples are collected daily and composited for quarterly analysis from the Clinch River at Center's Ferry near Kingston, Tennessee (Station C-5). Station C-5 is approximately 10 miles downstream from the Site. The con-centration of those radionuclides present as indicated by initial gamma ray spectrometry is measured by specific radionuclide analysis and further gama spectrometry. Analytical data for radionuclides found in the Clinch River as measured l by the Oak Ridge Environmental Monitoring Program during 1971 and 1972 are summarized in Table 2.8-5. The amounts found in the Clinch River I are substantially below the MPC's outlined in 10 CFR 20, Appendix B, 2.8-5

W WI7 Table II, Column 2 for each of the radionuclides listed in Table 2.8-5. C MPC's for Sr-90, Cs-137, Ru-106, H-3, Ce-144, Co-60 and Zr-95 are pre-sented in Table 2.8-5. In all cases, the average radionuclide concen-trations found are less than one percent of the MPC's. The tritium concentrations shown in Table 2.8-5 reported by the Oak Ridge Environmental Monitoring Program for the Clinch River can be compared to the concentrations found in surface water at the EPA-RAN stations for the April to June 1972 period. During this period, the average concen-tration for 39 RAN stations was 600 pCi/ liter.(9) This comparison indi-cates that the tritium levels in the Clinch River resulting from releases from ORNL facilities on an average are a factor of'three higher than the average level for the 39 RAN stations.(10) However, the highest concen-tration reported in Table 2.8-5, 5,080 pCi/l, is only 0.2 percent of MPC. Concentrations of other radionuclides are not routinely reported for the RAN stations. l Water samples for uranium analysis are collected in the Poplar Creek G upstream of the Oak Ridge Gaseous Diffusion Plant (Station P-1), in the

         ~

Poplar Creek downstream from the Diffusion Plant waste discharges (Sta-l tion P-2), in the Clinch River downstream from the Poplar Creek outfall (Staticn C-4), at the outlet of New Hope Pond on East Fork Poplar Creek (Station E-1) and on Bear Creek (Station. B-1). The Poplar Creek outfall in the Clinch River is approximately three miles downstream from the CRBRP site. Weekly samples are collected in Poplar Creek and composited for monthly analysis. Uranium analysis is perfonted by the fluorimetric rethod. Results of these analyses for 1971 and 1972 are sunnarized in Table 2.8-6. Maximum uranium concentration of 1,000 pCi/ liter observed in the surface streams in the Oak Ridge area is well below the 20,000 pCi/ liter MPC specified in'10 CFR 20, Appendix B, Table II, Column 2 for uncontrolled areas. Uranium concentration varies considerably among the five surface stream monitoring stations. In addition, there are also large variations (100 to 1,000 pCi/ liter range in 12 samples) among samples taken at the same station. 2.8-6

fvy7 [ Gross alpha and beta radioactivity in U.S. surface waters is obtained in a sampling and analysis program operated by the U.S. Environmental Protection Agency, Office of Water Planning and Standards. Values reported for the Clinch River at Kingsten, Tennessee, are given in Table 2.8-7. All levels are within MPC. Gross alpha and beth radio-activity measurements from the surface stream monitoring stations are not published. A sampling of the fish found in the Clinch River at CRM 14.5 was anlayzed for Sr-90 and Cs-137 and reported by the Oak Ridge Environmental Monitor-ing Pror; ram; 1971 data for Ru-106 are also included. The data for a composite of,10 fish in each species are given in Table 2.8-8. Assuming. an annual consumption rate of 14 pounds of fish per year per person, the percent of Maximum Permissible Intake (MPI) can be calculated for each radionuclide.(1,2) MPI is comparable to a daily intake of 2,200 ml of water containing the Maximum Permissible Concentration (MPC g ) for each ( radionuclide. (MPI pCi/yr = MPC pCi/ml x 2200 ml/da x 365 da/yr) Therefore,

.                   g gpy , uCi/kc x 14 lb/yr_ x 0.45 kg/lb x 100 MPI Values for % MPI shown in Table 2.8-8 are well below one percent.

Data on reconcentration of radionuclides by fresh water organisms have been reported by Jinks and Eisenbud.(10) The concentration factors (CF) were defined by the equation CF = gC g/C where gC is the concentration in the organism and C g is the concentration in the ambient water. Strontium concentration by fresh watcr fish is 0.85 to 90 with a mean at 14. Cesium concentration by fresh water fish is 120 to'22,000 with (' a mean of 3,680. These values are subject to large variations since b environmental conditions are not static. 2.8-7 i

The average Sr-90 concentration in Clinch River water from the data in Table 2.8-5 is 0.95 x 10-9 pCi/ml and 0.93 x 10-9 pCi/ml for 1971 and 1972, respectively. Using the radiochemical data in Table 2.8-8 for Clinch' River fish, the 1971 and 1972 concentration factors calculated for three species of fish are giv'en in Table 2.8-9. These data empha-size that concentration of Clinch River radionuclides by the aquatic biota must be considered in the evaluation of possible effects of .the CRBRP on the local environment. R. J. Pickering studied the distribution of radionuclides which were found in the bottom sediment of the Clinch River.02,13) Distribution of gross gama radioactivity as 'a function of depth along a core sample reflected not only the pattern of annual discharges of Cs-137 shown in Table 2.8-10 but also of Co-60 to a lesser extent. The distribution of gross gamoa, Cs-137, Co-60 and Ru-106 as a function of depth is shown by Figure 2.8-7. P. H. Carrigan, Jr.(13,14) made an inventory of the radionuclides asso-ciated with the bottom sediment of the Clinch River between the outfall to the Tennessee River and three miles upstream from the CRBRP. He con-cluded that in July 1962, 150 Curies of Cs-137,18 Curies of Co-60, 16 Curies of Ru-106,10 Curies of rare earth radionuclides and 2.9 Curies of Sr-90 were associated with the bottom sediment between CRM 0.0 and 21.0. Ninety-five percent of the activity was downstream from mile 15 and therefore downstream from the CRBRP. However, the largest single concentraticn occurred near the mouth of White Oak Creek which is up-l stream of the Site. High concentrations in this area are expected since dispersion of water and suspended sediments is restricted due to incom-i plete lateral diffusion. The concentrations at CRM 15, 16, 17 and 18 adjacent to the CRBRP, as shown in Figure 2.8-8, were high compared to I levels at CRM 1. 1 l (- 2.8-8

f'y Nj 17 Chemical and physical properties of the bottom sediment have been de-scribed. However, variations in annual releases and dilution of radio-active sediment by non-radioactive sediment prevents an accurate assessment of the impact. associated with the radioactive content of the Clinch River bottom sediment.'(I4) An earlier study sponsored by the Public Health Service, U.S. Department of Health, Education and Welfare, describes a similar distribution of radioat.tivity in Clinch River sediment with maximum activity near White Oak Creek outfall, see Figure 2.8-9(15) The relative contribution of each radionuclide to the total activity is approximately the same as reported by Pickering and Carrigan. However, the total quantities of each radionuclide reported for 1960 by the Public Health Service are approximately 100 to 1,000 times higher than those reported in the later studies. Data collected by the Health Physics Division, ORNL, for Clinch River sediment samples on July 29, 1972, August 5, 1972 and August 12, 1972 are shown in Table 2.8-11.(16) Distribution of activities in this study are similar to the above distributions reported by Carrigan and the Public Health Service. The sharp increase in activity below the White Oak Creek outfall is still evident in this data. The data indicates that Co-60 activity is maximum at CRM 5.8. Concentrations of Cs-137 l are still present and indications of a maximum can be seen at CRM 5.8. l Ruthenium concentration differences below White Oak Creek outfall are not nearly as pronounced. Maximum concentration of ruthenium at CRM 5.8 coincides with the cesium and cobalt maxima. Retention factors for Clinch River sediment have been calculated by Carrigan to be 9 percent for Co-60, 21 percent for Cs-137 and 0.2 percent forSr-90.(I4) Retention of radionuclides is not expected to limit the usefulness of the Clinch River to nearby facilities. 1 2.8-9

f"y1417 .

                                                                                 ~

conceivable. Large differences in the Sr-90 concentrations found in milk collected from the sampling stations during atmospheric fallout and during normal periods suggest that significant differences in feed sources and feeding routine might exist. Consistently higher values in the imediate environs for the two years suggests that the input to the grass-cow-milk-man pathway continued in these years. I-131 values were not routinely reported since levels at the majority of the network stations were below practical reporting levels. 2.8.5 GAMMA BACKGROUND As part of the Environmental Monitoring Program for the Oak Ridge facili-ties, gama background measurements were taken once each five weeks during servicing visits to the remote air monitoring stations which are shown in Figure 2.8-3. Measurements were made using calibrated G-M and scintillation-type detectors at a distance of three feet above ground surface. Background levels observed during 1971 are given in [' Table 2.8-19. The average level of 9.3 uR/hr is equivalent to 71 mrem per annum. This level can be compared to the estimated average external gamma whole body doses to the population in Tennessee, North Carolina, South Carolina and Virginia from natural terrestrial radioactivity of 70, 75, 70 and 55 mrem per annum, respectively.(22) Terrestrial and cosmic radiation measured by aerial survey over Knoxville, Tennessee was reported by the EPA to be 104.0 mrem /yr.(23) TVA, using film badges and thermoluminescent dosimeters, have reported gamma back- ~ ground measurements in the Oak Ridge area as 110 mrem /yr.(24) l Information on the exposure rate at several locations for the surface of the sediment in the Clinch River and the Tennessee River is given in i Tables 2.8-20 and 2.8-21, respectively. Gamma exposure rates in some areas of the Clinch River are three to four times higher than the aver-age backgmund levels shown in Table 2.8-19. All locations sampled at 2.8-12

f't!97 C the surface of the Tennessee River silt were at or below background levels. Measurements of gamma exposure rates were discontinued in 1969. 2.8.6 OTHER SOURCES OF RADIATION EXPOSURE Various components of the average annual genetically significant dose to the population in Tennessee for 1970 are presented in Table 2.8-22. It is apparent that the radiation exposure to the public from natural-sources and medical applications is quite large and that the relative contribu-tion to the' total population from operation of the Oak Ridge Facilities is small. 2.

8.7 CONCLUSION

S The area surrounding the Clinch River Site is presently characterized by air and aquatic radioactivity levels that are well below maximum permissible concentrations (MPC's) as outlined in 10 CFR 20, Appendix B ( for unrestricted areas. Any significant releases of radioactivity from the CRBRP into the air or into the Clinch River water should be disting-uishable from the present background levels by the effluent and environ-mental monitoring programs discussed in Section 6.0. In addition, any significant exposure of man to radioactivity through the food chain should also be detectable since present iodine levels in locally produced milk are well within Federal Radiation Council guidelines and the radionuclide content of fish is well below maximum permissible intake (MPI). Continued monitoring of soil and other terrestrial products for plutonium should result in detection of possible releases from the CRBRP. Studies made of the Clinch River sediment indicate that the total radio-nuclide inventory may be substantial. However, since these inventories have not made significant contributions to the activities present in the Clinch River water nor to the radionuclide content of Clinch River fish, ( 2.8-13

pyeof/7 I . l

                                                                              ~.

it may be assumed that present radioactivity levels in the Clinch River sediment present no potential hazard to man. In conclusion, the background radiological characteristics have been adequately characterized to allow' detection of releases from the CRBRP which may significantly impact the environment. 4 Ne 2.8-14

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• TABLE 2.8-11 RADIONUCLIOES IN THE CLINCH RIVER SEDIMENT 06) pCi/g Clinch River Mile Date Co-60 Ru-103-106 Cs-137 4.7 8/5/72 3.2 0.9 25.0

                                             ~

5.8 8/5/72 3.8 1.4 59.0 8.0 8/5/72 2.0 1.4 22.0

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TABLE 2.8-21 AVERAGE GAMMA COUNT RATE AT THE SURFACE OF TENNESSEE RIVER SILT Gamma Activity--Counts Per. Second Loc ion (48 c/s = 4 0.03 mR/hr Cross Section 1966_ 1967 1969 TRM 570.8 8.9 8.7 8.3 567.6 Entry of Clinch River 562.7 17.3 16.3 15.1

                                                                             ~

552.7 17.9 12.6 16.4 543.8 12.8 15.5 11.6 532.0 11.5 11.5 11.'2 . 530.0 Watts Bar Dam

                                             *

• 6.5

           .         509.5 12.6

• 11.5 491.9

                                             *

• 10.7

      /              475.1 471.0                            Chickamauga Dam

! 434.1 *

• 7.8 l

425.2 *

• 8.6 l

425.0 Nickajack Dam 404.0 *

• 3.2

                                             *

• 8.9 381.2 354.4 C.5
• 8.8 349.0 Guntersville

        *No measurements taken Note: No survey made in 1968 l'

i L 2.8-35

TABLE 2.8-20 f9st-ll7 - AVERAGE GAMMA COUNT RATE AT THE SURFACE OF CLINCH RIVER SILT (33)

                                                                           ,?

Gamma Activity--Counts Per Second Location (48 c/s = % 0.03 mR/hr of - Cross Section 1966 1967 1969 CRM 51.6 *

• 8.1 -

50.5 Entry of Braden Branch 48.8 *

• 19.2 42.8 7.3 7.8 14.8 39.1 *
• 18.4 34.7 7.4 7.0 20.1

                                    '6.8 31.1                                 6.8        18.2 29.0                  *

• 18.7 27.0 *
• 15.2 24.9 6.7 7.3 20.5 23.1 Melton Hill Dam .

21.5 5.0 2.9 2.4 20.8 Entry of White Oak Creek 19.1

• 8.0 7.4 17.8
• 11.9 11.9 16.3 35.1 16.8 12.0 15.2
• 28.3 12.7 14.0 37.3 2819 28.7 12.5
• 13.5 11.5 11.0 63.1 '

48.0 30.9 9.4

• 19.7 18.4 8.0 68.8 60.1 51.5 5.8 67.8 57.0 56.0

! 4.7 46.9 36.7 37.3 1.1 46.6 42.0 39.8

 *No measurement taken tiote: No survey made in 1968 i

2.8-34

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          ^               '

p [' ECONDS CONTENT,IN PICOCURIES PER GRAM 10 0 200 300 400-50 0 100-50 0 10 0 *

        -10             0     10 20  30 40 50 -50 O O

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. M T ['7 C

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O 50 0 22 20 18 16 14 12 10 8 6 4 2 O CLINCH RIVER MILE Figure 2.8-8 LONGITUDINAL DISTRIBUTION OF RADIONUCLIDES IN ' BOTTOM SEDIMENT OF THE CLINCH RIVER (14) 2.8-45

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                                                                     ^        ^ Co60

: Sr'0 Figure 2.8-9 RADIONUCLIDE CONGENTRATIONS IN BOTTOM MUDS, CLINCH AND TENNESSEE RIVERS (15) 1 1

2.8-46

Sjla 7A TO: Dave Goeser/WLLCO FROM: Henry Piper /CRERP/PO lyg [M

Subject:

"Old" ER References                    a.

6 l 4 l O

                           "Old" ER References

1. References. We are working from the ref erence ER updated by Amendment 8.

1.1 Reference 12, Pickering, R. J., as:

12. Pickering, R. J., Distribution of Radionuclides in Bottom Sediment of the Clinch River, Eastern Tennessee, Geological Survey Professional paper 433-H, U.S.

Government Printing Office, Washington, DC, 1969. found on page 13.0-25. This page had had no revisions to that date. , 1.2 Ref erence .13, ORNL-4035 (EG Straxness) , same page as reference 12, above:

13. Oak Ridge National Laboratory, Health Physics Division, Comorehensive Reoort of the Clinch River Stud?,

ORNL-4035, Oak Ridge, TeEhessee, April 1967. 1.3 Reference 14, P. H. Carrigan, Jr. same page as ref erence 12, above: ,

14. Carrigan, P. H., Jr., Inventory of Radionuclides in Bottom Sediment of the Clinch River. Eastern Tennessee, Geological Survey Prof essional paper 433-I, U.S.

Government Printing Office, Washington, DC, 1969. 1.4 Reference 15, USPHS,'same page as 12, above:

15. Friend, A. G., et al, Behavior of Certain Radionuclies Released Into Presh Water Environments: Annual Reoort, 1959-1960, National Center for Radiological Health, U.S., Department of Health, Education and Welfare, Rockville, Maryland, June 1965, pp 47-49.

1.5 Reference 16, H. P. Division, ORNL, same page as 12 above:

16. Letter with Appendices, Davis, D. M., Oak Ridge National Laboratory to Herr, H. F., WESD, 27 July 1973.

1.6 Reference 33, USEPA, page ER 13.0-24:

33. U.S., Environmental Protection Agency, Radiation Date and Rec _ orts, Vol 13, June 1972, pp 361 and 369.

2. Legend 2.1 Page 2.8-1, in the first paragraph states the fact of historical release to the Clinch River.

2.2 Page 2.8-8 cites the rediment studies by Pickering and the ORNL waste management research group headed by Dr. E. G. Struxness. Data are seen in Figure 2.8-7. 2.3 Likewise, P. H. Carrigan's cooperative work with Straxness' group is cited on page 2.8.8. The data are seen in Figure 2.9-8. 2.4 On page 2.8-9 an earlier work on measuring Clinch River sediment' radioactivity by the U. S. Public Health Service-is cited. Data are seen in Figure 2.8-9. 2.5 Later ORNL sampling of sediment is reported on page 2.8-9 and the data are seen in Table 2.8-11.. l 2.6 Pickering's study as stated on page 2.8-8, showed ~ correlation with annual discharges as recorded in Table 2.8-10. l . 2.7 Silt measurements in the Clinch and Tennessee river apparently corresponding to river bank or low water access to sediment are discussed on page 2.8-12 and data seen in Tables 2.8-20 and 2.8-21. Data is semi-quantitative. This work was done by USEPA, successor to USPHS. e I

   , - , -   w - - -     -.,.-Q m.- -_ -      -

          .                                                                                                                        APPENDIX C                                -

i Implementation of the construction drainage .pla. .n will limit sediment loss- , .. through site disturbance. The Clinch, River and Roberts Branch are

                                                                                                                   ~

the two watercourses that would conceivably be affected by. runoff from .

                    ' " construction activit,ies.                                    .                      .               ...        . . .              :          .                         .-

Increases in total suspended. solids, biochemical' - oxygen demand, and nutrient concentrations will be minimized in the localized areas of these waterways, through implementation of the best - management practices. Compaction of fill' materials, seeding and - '

                   . mulching of completed areas, and construction of sediment traps will
              . .shinimiz'e site runoff and its impa' cts. The duration of any impacts will                                                                                                     .-
 ~
            .             be generally limited to the site preparation and facility construction -                                                                                                               '.--e
    ' ' , phase.
                                                                          '                     ~
                                                                                                     ",                              '                      '                                                                         ~

r' '.

     -                                                                                                       -                                                          ' ' ~                         '
 '@   .W. ,:.5           .S.5i2.2... t 2.2 J s !!OrYanno e? 'iid @              A_
                                                                    -m                                                                                           ..
                                                                                                                                                                 .g ..-                .                                              . ;,
              "#                                           ~        ~

CoEtIu~ciio'n 'Tif tAe water intake structure for the facility, *the .

 "T ^ - structures for the effluent- diffusers,- the railroad bridge and the temporary construction barge facilities . will temporarily , impact.~ river                                                                                          .
                    . water quality.                   Impacts will generally be related to dredging activities                                                                            -
                                                                                                                                                                               ~

J. - necessary to cor;struction of these structures.

                                       .                 .                                                                 Water ..        quality           'mpacts i                  i.'

wi!I. be,,short-term. , occurring primarily ,during the , actual dredging

   ; ., ' operat.ions.                                                                        .

The schedule for underwater work in the

                                                                                                                     ,- Clincih River is flexible                          ,

and can be modified to accommodate environmental concerns. Dredging

• and construction of the railroad bridge caissons will be completed as - -

quickly as possible once such work begins. . Clinch River sediments I'n the general area of the proposed TSA site have been the focus of several published and unpublished studies. - l These include the Clinch River Study -(Struxness 1967), and USGS, AEC, O'RNL study (Pickering 1969), unpublishedf core. sample data '.1,., collected in 1977-1980 analyzed by ORNL, and environmental monitoring , ._ d' ,

 ;                        report data from the Oak Ridge Gaseous Diffusion Plant (Union Carbide                                                                                                  '
                                                                                                                                                                                                                   *3

• f'

( Nuclear Division 1980). Current ORGDP sediment sampling location's are d e indicted in Figure 5.2.2.2.2-1; data reported for those stations, fon '3 s , 1979, are presented as Table 5.2.2.2.2-1. Figure 5.2.2.2.2-2 shows the locations for sediment stations for the unpublished data; those data

                                                                                                                                                                                                        ~-

c__. are tabulated in Tables 5.2.2._2.2-1 through 5.2.2.2.2-6. Review of the .. 4 5-34

                                                                                                                     -A                \D
                             ~

C. N s* + ,Psts p' .. , , , J

                                                        '                        A

• mz ms
• Ps17 f

zan 1 %%s F822 , i. 4

                                                 =            '              '       " L v

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                       .'                       g==                 alc.,.s                         .

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                                                          "*                *                           .h uyan
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                                         *L        ,,y .

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                            . - r.xisting oncm.                                                                          .:                    ,,

Stations .2 .-

                                                                                          \
                                                                                                                                      ]

A - Proposed TSA Borings [ .-_-. - Figure 5.2.2.2.2 1 Sediment Sampling Site Locations

                                                                                                                                   ~~.

1 ,

                                                                 =

o 5-35

TABLE 5.2.2.2.2-1 .

                                                                                                                                                                                                                                  ,, [

STREAM SEDIMENT SAMPLES .. JULY / NOVEMBER 1979 - ~ AVERAGE CONCENTRATION (pg/g DRY WElGHT BASIS) Station U Hg* Pb Ni Cu Zn Cr Mn .Cd Al Th CS1 2 <0.2 33 30 15 48 25 985 <5 26,000 <40 PS2 17 35 63 135 110 163 219 600 <5 93,000 <40 PSS 5 <0.3 48 88 31 103 60 360 <5 60,000 <40 PS6 . 14 11 54 147 45 172 224 525 <5 52,500 <40 PS9 6 3 40 61 . 92 82 50 570 <5 34,500 <40 PS10 4 3 40 79 29 84 77 810 <5 34,000 <40 PS12 17 <9 44 75 34 104 98 813 <5 43,500 <40 PS15- 14 6 43 109 39 97 62 523 <5 39,500 <40 PS17 181 <13 76 790 412 237 97 570 <5 52,000 <40 Y PS18 6 4 48 103 38 84 59 496 <5 36,500 <40 E. PS19 17 21 54 120 43 95 88 422 <5 P.9,000 <40 PS21 7 <1 68 110 81 124 101 543 <5 /3,000 <40 PS22 12 7 65 157 44 103 88 l 513 <5 34,000 <40 CS20 1 ,

                                                              <0.2                   37                                                                 26       65         47    244          386           <5       26,500  <40 8

Average of two samples, some results were below detectable limit. Ref: Union Carbide Nuclear Division 1980. '

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                                                                                                                                            .. e -

Figure 5.2.2.2.2 2 Location Map for Unpublished ORGDP - Sediment Data ( ~ 5-37

hMW TABLE 5.2.2.2.2-2 i

                                                                                                                   ~

UNPUBLISHED OAK RIDGE GASEOUS DIFFUSION w PLANT SEDIMENT DATA 1980 (Nov) (July) (Nov) (July) Location Uranium (ppm)

• Mercury (ppm) 2 4.46 11.70 9.2 18.1 . . . , .

5 2.22 9.58 2.2 3.0 6 30.00 9.80 21.6 8.1 4 9 1.57 5.68 0.9 2.6 [' , 10 27.40 5 95 _ 21.2 9.7 12 4.45 7.00 6.5 17.0-15 58.50 12.70 8.2 16.6 17 . 19.50 3.88 .,, 11.8 -. 5.3 -' 18 3.80 2.95 11.6 0.4 l 19 13.10 5.82 2.0 11.0 20 <0.001- 4.39 <0.02 8.4 l 21 5.16 4.24 4.2 25.4 e.

                                                                                                    , e : :.

a <

                                           ^

4

                                                                              .                   3
                                                                                                  =

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                                                                                              "[E ,

5-38 4 --

G  % TABLE 5.2.'2!,2.2-3

  .                   UNPUBLISHED OAK RIDGE GASEOUS DIFFUSION PLANT SEDIMENT DATA 1979 (Nov)        July)           (Nov)             (July)

Location Uranium ((ppm) Mercury (ppm)

                       ~

2 18.03 , 15.50 29.6 40.0 5 7.38 4.58 2.3 O.3 - 6 5.34 17.70 <0.2 - 7.5 9 10.14 5.85 15.1 4.9. 10 5.26 4.26 1.8 3' . 2 12 ,, 4.38 32.10- 2.4 17.9 15 6.73 11.50 2.9

                                                                .                      4.5 17                  2.91    260.00            ,< 0.2              26.0              -

() 18 19 102.80 16.42 808 14.60

                                                            <0.2 6.7 5.0 15.0                          -

20 4.16 1.21 2.0 <0.2 21 20.22 7.12 26.5 <0.2 e4

4 .,

                                                                                              .a 4

1 .

                                                                                                           ?

e = 09

                                                                                                     .*                   9 5-39

. . l4% 1 T A B L E 5. 2. 2. 2. 2 '4 1, UNPUBLISHED OAK RIDGE GASEOUS DIFFUSION PLANT SEDIMENT DATA 1978 (Nov) (July) ' (Nov) (July) Location Uranium (ppm) Mercury (ppm) 2 20.0 9.58 7.2 8.06 ,,, 5 10.8 7.80 2.52 1.71 6 6.3 22.30 3.19 12.10 - 9 2.5 5.88 4.63 1.14 ." 10 8.4 34.60 6.95 28.0 ' 12 11.8 21.40 7.38 4.48 15 76.1 115.50 25.2 16.40 17 20.7 3.19 ,,, 4.52-~

                                                                     <0.02 18             5.18         6.98                     7.54         2.82 19             4.23        14.00                     2.88        25.40 20             4.8

• 14.60 2.67 2.66 21 8.8 18.00 0.34 11.6 es g*

J? ii *

                                                                                           .h             '

3_ emme 4_5-C 5-40

  ~ L, ,' . .                                                                                                              \% '

l l i TAB LE 5.2.2.2.2 '

     ..)                 UNPUBLISHED OAK RIDGE GASEOUS DIFFUSION PLANT SEDIMENT DATA 1977 (Nov)         (July)           (Nov)             (July)

Location Uranium (ppm) Mercury (ppm) 2 12.80 8.0 10.26 .,

                                                                              . 8.00               .

5 6.48 3.33 1.40 3.33 6 72.2 4.84 38.00 4.84 9 43.70 1.62 21.50 .1.62 10 8.50 5'.24 1.35 1.35_ . 12 3.30 5.75 10.02 / 5.75 15 - - - - 17 - 9,.,61 11:00 9.61

                                                                                                                     ~

.O 18 10.70 13.50 8.97 13.50 19 - 18.50 21.90 18.50 20 - - - - - 21 - - - - l l .

                                                                                                               ' ? *4
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E

                                                                                                         .y               -.

t o 5-41 w

I-

    , . , , ,                                                                                                                       lg TABLE 5.2.2.2.2-6                                                                      .

UNPUBLISHED OAK RIDGE GASEOUS DIFFUSION PLANT SEDIMENT DATA . - PCB ANALYSIS ON POPLAR CREEK Lccation (see map) PCB (pg/g) 1 <0.1 2 "'

                                                                    <0.1                                            ~~.'-

3 0.19 ' 4 <0.1 ' ' 5 0.16 6 <0.1 ,' 2 7 0.48 8 <0.1 ~. 9 <0.1 10 0.24 -

                                                                       ~   ~

11 -

                                                              ...   <0.1 12                                                   <0.1                                                             '

13 12.00 14 6.00 15 - 14.00 16 12.00 17 15.00 i 18 1.5 19 .

                                                                    <0.1 20                                                   <0.1                                                   -
                                                                                                                        , ::4 21 0.3                                            .y 22                                                    0.3                                 -

a' 3 23 0.4 4 l ~.! 3 l -- \

                    -                                                                                         ..r.
                                                                                                                   - g_ - - - -

C

         -                                               5-42

-                           ~
                                                                                                      \D                  $%

RW & ' data from these above . studies suggest that concentrations of the radioisotopes studied in the Clinch River sediments are at a very low level; that the distribution of the isotopes appears stable with time; and.

               .that the risk to humans from these sources appears to be very low.r The , planned dredging operations; related to site preparation' and to facility construction, will result in movement of certain quantities of.,

the sediments. - The- combination , of low con'tamination levels and.. apparent immobility of the contaminants suggest a low risk situation. A program to obtain and analyze sediment samples for radioisotopes in the Clinch River adjacent to the proposed site is ' in progress. '. $ " Seventeen borings are included in the program: two ,in the general vicinity of previous TSA obtained sediment samples and at least one every one-half mile around the perimeter of the Figure - site.,.. 5.2.2.2.2-1 shows the locations of the radioisotopes proposeb borings.' The samplings are being performed in the exact same manner as that used in the 1967 ~ and' 1977 studies mentioned above. Results should, therefore, be directly comparable to those studies's results. The.

        '        proposed program will be reviewed by both' the U.S. DOE and ORNL.
                              -                                        _-   ..                      5 C

5'.2.2.2.3 Sanitary Wastes Sanitary wastes generated during the site preparation and -

          ,     construction stages will be hauled off-site by a permitted waste disposal handler and disposed of at an approved treatment facility. Therefore, no impacts on Clinch River water quality are anticipated.

r 5.2.2.2.4 Railroad Bridge Construction' of the railroad bridge across the Clinch River is - expected to have limited' impacts on river water quality during the

                                                                                                                   .; .,y dredging and construction phase.              Impacts will be related primarily to.           _j increased         suspended    solids associated with handling of dre'dged                  'i-materials.                                                                                               ':

(( . 2 Y "N

                                                                                                                            ~
                                                                                                           '3 ~F- } .

I ( '

          .                                                5-43
                                                                                                                             /

a

   ~

APPENDIX D i CLINCH RIVER BREEDER REACTOR PROJECT PRELIMINARY SAFETY ANALYSIS _ REPORT - 2

c. .

CHAPTER 15 ACCIDENT ANALYSIS , PROJECT MANAGEMENT CORPORATION O e

\

e

o TABLE 15.1.2-1 EVENT CLASSIFICATION AND CLADDING DAMAGE SEVERITY LIMITS Event Classification Severity Level ASME Code section !!! RDT 5tandard C-16-1 RDT 5tandard C-16-1 (Article NR-3113) Normal: Nomal Operation: No Damage: Any condition of system startup. Normal operation includes No damage is defined as 1) no design range operations. not steady po.er operations and significant loss of effective standby, or chutdown other than those departures from steady fuel lifetime; 2) accomodations an upset, emergency. faulted or operation which are expec+?d 'within the fuel and plant testing conditions. frequently or regular 1; en operating margins without the course of power .perations, req"* ring automatic or manual refueling, maintenance, or pro. sctive action; and 3) no maneuvering of the plant. planned release of radioactivity. , Upset: Anticipated Faulted: Operational Incident: Any abnormal incident not An off-normal condition etich An operational incident is causing a forced outage or individually may be expe6ted defined as an occurrence which causing a forced outage for to occur once or more during results in 1) nn reduction of which the corrective action the plant lifetime, effcetive fuel lifetime below does not include any repair the design values; 2) accom o-of mechanical damage. dation with, at most, a reactor trip that assures the plant will be capable of returning to operation after corrective action to clear the trip cause; and/or 3) plant rtdioactivity releases that may approach the 10CFR20 guidelines. Emergency: Unlikely Faulted: Minor Incident: ,- Infrequent incident requiring An off-normal condition which A minor incident is defined as shutdown for ccrrection of ,- individually is not expected an occurrence which results in the condition or repair of to occur during the plant life- 1) a general reduction in the damage in the system. No time; however. when integrated fuel burnup capability and. at loss of structural integrity. over all plant components, most, a small fraction of fuel - events in this category may be rod cladding failures; expected to occur a nunter of 2) sufficient plant or fuel times, rod damage that could preclude F resunction of operation for a considerable time and/or

3) plant radioactivity releases that may exceed 10CFR20 guide-i lines. but does not result in interruption or restriction of public use of areas beyond the exclusion boundary.

Faulted: Extremely Unlikely Faulted: Major Incident: Postulated event and conse. An off-normal condition of A major incident is defined as quences where integrity and such extremely low proba- en occurrence which results in operability may be impaired bility that no events in this 1) 3ubstantial fuel and/or to the extent that consid- category are expected to 3ccur cladding melting or distortion trations of pihlic health during the plant lifetime. but in individual fuel rods, but and safety are involved. whicn nevertheless represents the configuration remains extreme or limiting cases of coolable; 2) plant damage that failures unich are identified . may preclude resunction plant as design bases. operations. but no loss of safety functions necessary to cope with the occurrence; and/or 3) radioactivity release - that may exceed the 10CFlu0 guidelines but are well within the 10CFR100 Cuidelines. l / 15.1-72 l

D - F e

                               ~

[ ' gMo Q % _ D - c. m TRANSIT 10 - O h4 , gygge,

                     ;         :           ':=>              _ _ _ m_                _____                       ______a                -

O_ g ~ 1298*F E * - g f3 '.J00*F 1300*F a 91100*F TEST

      'a f IN G

_ 01200*F > TERAPERATURE. g 9130f' F CLOSEb SYMSOLS i 0

                              ~                                                                                                                              1488*FO h                 .             di4te*F          FOR Tg,, >Ty ,                                                           1530'F 3                                        Jo, = 89,485 esp   8595 a1 d T y a = KSt                                                                                '

1600*F g ~ P0lNT OF TRANSITION: lt, = 5,9150 m Id eup @57. N/Th,,t, = hr E 4

                              ~ FOR o,20,: SMF] = 0.4292 x 18 -7782.1 le(o,). O, = KSI g       _ F0R o,<o :n[LMP3 = 4.427s = 1s4 + 2.2serrg-me i. (g)

LARSON MILLER PARAMETER: [LMP)Tg {29 +%gg(t,)} Tg = % ) g i i I I l 'I l l i I I IIitI i I  : ::  : g g,,,, , , ,,,g,,, e 1.s is. ise,e i s,,, ,, TIME TO RUTTURE (lu) Figure 15.1.2-1. Stress-Rupture of 20'J. Cold-Worky.116 Stainless Steel . . . Irradiated:0.2 0.9 x 1022 n/cm2 g > 0,1 Mey \ b

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

                                                 )

In the Matter of )

                                                 )

UNITED STATES DEPARTMENT OF ENERGY )

                                                 )

PROJECT MANAGEMENT CORPORATION ) Docket No. 50-537

                                                 )

TENNESSEE VALLEY AUTHORITY )

                                                 )

(Clinch River Breeder Reactor Plant) )

                                                 )

CERTIFICATE OF SERVICE Service has been effected on this date by personal delivery */ or first-class mail to the following:

         *** Marshall E. Miller, Esquire Chairman Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C. 20545 Dr. Cadet H. Hand, Jr.

Director i Bodega Marine Laboratory l University of California l P. O. Box 247 l Bodega Bay, California 94923 l

         ***Mr. Gustave A. Linenberger Atomic Safety & Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C. 20545

• Daniel Swanson, Esquire

           *Stuart Treby, Esquire Office of Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C. 20545 (2 copies) l l

• Atomic Safety & Licensing Appeal Board

. U. S. Nuclear Regulatory Commission Washington, D. C. 20545

• Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20545
• Docketing & Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. C. 20545 (3 copies)

William B. Hubbard, Esquire Assistant Attorney General State of Tennessee Office of the Attorney General 422 Supreme Court Building Nashville, Tennessee 37219 Oak Ridge Public Library Civic Center Oak Ridge, Tennessee 37820 Herbert S. Sanger, Jr., Esquire Lewis E. Wallace, Esquire W. Walter LaRoche, Esquire James F. Burger, Esquire Edward J. Vigluicci, Esquire Office of the General Counsel Tennessee Valley Authority 400 Commerce Avenue Knoxville, Tennessee 37902 (2 copies)

 **Dr. Thomas Cochran Barbara A. Finamore, Esquire Natural Resources Defense Council 1725 Eye Street, N. W., Suite 600 Washington, D. C. 20006 (2 copies)

Mr. Joe H. Walker 401 Roane Street Harriman, Tennessee 37748 Ellyn R. Weiss Harmon & Weiss 1725 Eye Street, N. W., Suite 506 Washington, D. C. 20006

3-Lawson McGhee Public Library 500 West Church Street Knoxville, Tennessee 37902 William E. Lantrip, Esq. Attorney for the City of Oak Ridge Municipal Building P. O. Box 1 Oak Ridge, Tennessee 37830 Leon Silverstrom, Esq. Warren E. Bergholz, Jr., Esq. U. S. Department of Energy 1000 Independence Ave., S. W. Room 6-B-256, Forrestal Building Washington, D. C. 20585 (2 copies)

               **Eldon V. C. Greenberg Tuttle & Taylor 1901 L Street, N. W., Suite  805 Washington, D. C. 20036 Commissioner James Cotham Tennessee Department of Economic and Community Development Andrew Jackson Building, Suite 1007 Nashville, Tennessee   37219
                                             //M          /'

G'eorg A . Edge 6 Attorney for Proj ect Management Corporation DATED: March 19, 1982

 */   Denotes hand delivery to 1717    "H" Street, N.W., Washington, D. C.
 **/ Denotes hand delivery to indicated address.
 ***/ Denotes hand delivery to 4350 East-We'st Highway, Bethesda, Md.

l

                 -       -}}