513 F.2d 1045 | D.C. Cir. | 1975
Opinion for the Court filed by Circuit Judge Robinson.
We are summoned to review an order of the Atomic Energy Commission, predecessor of the Nuclear Regulatory Commission,
I
Nuclear power reactors typically generate thermal energy through a process of controlled fission reaction in the reactor core.
On February 20, 1971, the Atomic Energy Commission adopted, for effective operation the following May, a bundle of “General Design Criteria”
Shortly thereafter, on November 30, 1971, the Commission launched a comprehensive rulemaking proceeding to enable further exploration of scientific opinion as to possible refinements of the Interim Acceptance Criteria.
II
Petitioners’ current effort did not originate as a part of the administrative litigation concerning requirements for emergency core cooling systems. They were not participants in the proceeding forerunning promulgation of the General Design Criteria, or that following publication of the Interim Acceptance Criteria,
The first attack came in an action in the District Court for the District of Columbia wherein petitioners sought injunctive relief against further operation of the reactors and ultimately the revocation of the licenses authorizing their use.
Petitioners then turned to the Commission for the shutdown,
Against this backdrop, the Commission addressed petitioners’ claim that the plants in question should be shut down because compliance with the Acceptance Criteria did not “assure” the effectiveness of the emergency core-cooling systems:
Neither the statute nor the Commission regulations in issue . . . require such an unattainable guarantee of risk-free operation. . . . We do not live in a risk-less society, nor could modern technological societies exist on that basis. We are, of course, aware of the potential risks in nuclear matters if safety is not given the very close attention it deserves. In this regard, the [loss-of-coolant accident] has been characterized as “perhaps the most-studied hypothetical accident in history”44 . . . . These studies continue. It is precisely because of this perceived risk that we have always imposed stringent and overlapping protective measures in implementing the concept of defense in depth. However we cannot — and do not — claim “assurance” as an absolute.45
“Rather,” the Commission continued, “the regulatory process turns upon the concept of ‘reasonable assurance’ to public health and safety.”
The Commission then found that “[m]easured by this standard, reactors operating under the [Interim Acceptance Criteria] provide reasonable assurance of protection to the public health and safety in the highly unlikely event of a major loss-of-coolant accident.”
Petitioners case ignores the substantial showing of scientific and engineering support for the [Interim Acceptance] Criteria. •. . .Of course there is a variety of expert opinion in the [emergency core-cooling system] rule-making record — ranging from those who take the view that even the Interim Criteria are too conservative to those few who have reservations about some aspect. None of the experts upon whom petitioners rely supports the extraordinary relief they seek. . We have not been shown, nor have we found, any factual basis which would warrant short-circuiting the orderly culmination of the [emergency core-cooling system] rulemaking proceeding. On the record presented in the instant case, we specifically reaffirm our conclusion that compliance with the [Interim Acceptance Criteria] provides reasonable assurance that emergency core cooling systems will adequately protect the public health and safety.48
Accordingly, the Commission concluded that there was “neither an ‘undisputed
Ill
To establish the basis for our consideration of the petition for review, we pause briefly to identify the perameters of our inquiry and the legal criterion by which we measure the Commission’s action. The shutdown petition did not ask for an administrative hearing, nor was such a hearing required
The theme of the petition for review is that the Commission’s refusal to order a shutdown was “not in accordance with law.” The “law” allegedly dishonored is the call by General Design Criterion 35 for “a system to provide abundant emergency core-cooling.”
To be sure, an administrative agency is bound not only by the precepts of its governing statute but also by those incorporated into its own regulations,
As a precondition to grant of a license for operation of a nuclear facility, the Atomic Energy Act explicitly requires a Commission finding that the licensed facility will afford “adequate protection to the health and safety of the public.”
The reasonable assurance standard is the hallmark of many of the Commission’s safety regulations,
More importantly, it is evident that the General Design Criteria, as their name implies, were intended to provide engineering goals rather than precise tests or methodologies by which reactor safety could be fully and satisfactorily gauged. From the very beginning, the Commission acknowledged that they merely “establish[ed] minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission.”
The development of these General Design Criteria is not yet complete. For example, some of the definitions need further amplification. Also, some of the specific design requirements for structures, systems, and components important to safety have not as yet been suitably defined.70
And the Commission warned “that the criteria will be augmented and changed from time to time as important new requirements for these and other features are developed.”
So it was that, only about five weeks after the effective date of the General Design Criteria,
The compatibility of the emergency core cooling systems of the challenged reactors with the Interim Acceptance Criteria is not at issue in this case.
We think, too, that the Commission has made the essential findings. When the Acceptance Criteria were announced, the Commission made known its belief “that these criteria for emergency core cooling systems provide reasonable assurance that such systems will be effective in the unlikely event of a loss-of-coolant accident.”
We realize, of course, that none of these pronouncements states in haec verba that compliance with the Acceptance Criteria is likewise compliance with Criterion 85. But to say that that particular formulation was necessary is to completely ignore the critical relationship between the two sets of regulations. And in view of their common purpose to execute the statutory mandate of reasonable assurance of adequate protection to the public health and safety,
IV
We are mindful of petitioners’ opposition to that conclusion on the ground that some witnesses testifying in the rulemaking proceeding envisioning permanent criteria criticized the Interim Acceptance Criteria and urged more stringent standards. One might, at the outset, question the underlying logic of petitioners’ position in that regard. If the Commission must shut down or derate extant reactors whenever it hears testimony adverse to their integrity — particularly in a rulemaking proceeding addressed specifically to whether additional safety precautions are needed — it can never progress toward greater safety regulation without calling into question its own performance to date. As the Supreme Court has observed, “nuclear reactors are fast-developing and fast-changing. What is up to date now may not, probably will not, be as acceptable tomorrow.”
More fundamentally, however, acceptance of petitioners’ argument would inexorably draw us into a collateral review of the Acceptance Criteria themselves. That would be our posture although at no time have petitioners participated in any of the proceedings considering standards for emergency core cooling system performance, or sought direct judicial review of any standards promulgated by the Commission on that score.
These difficulties are compounded by another factor prominent in the case at bar. The shutdown petition sought emergency relief of a drastic nature pending reconsideration of the Interim Acceptance Criteria in the rule-making proceeding in progress. In that milieu, and upon consideration of the administrative record, the Commission perceived no “factual basis which would warrant short-circuiting the orderly culmination of the [ongoing] rulemaking proceeding.”
We readily find that support in the administrative record here.
In sum, we have no reason to disturb the Commission’s conclusion that the emergency core cooling systems under attack met the Interim Acceptance Criteria.
Petition dismissed.
. See Energy Reorganization Act of 1974, Pub.L. No. 93-438, tit. II, 88 Stat. 1233, 1242-1248 (1974). Our review is unaffected by the transfer of functions from the one agency to the other while this case was under submission. Id. tit. Ill, § 301(d), (f), 88 Stat. 1249 (1974). References herein to the “Commission” are, of course, to the Atomic Energy Commission.
. See note 8, infra, and text infra at notes 4-11.
. Petition for Shutdown of Certain Reactors, 38 Fed.Reg. 23815 (1973), hereinafter “Shutdown Petition.”
. See Atomic Energy Commission, Final Environmental Statement Concerning Proposed Rule Making Action: Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Cooled Nuclear Power Reactors, Docket No. RM-50-1, at 8-16 (1973), hereinafter “Environmental Statement.”
. The core of a nuclear reactor is the central portion containing the fuel elements.
. Environmental Statement, supra note 4 at 13-14.
. Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Cooled Nuclear Power Reactors, Docket No. RM-50-1, at 6 (Dec. 28, 1973), hereinafter “Acceptance Criteria.” The defense-in-depth principle embraces three levels of safety to prevent and control the effects of a wide spectrum of postulated hypothetical accidents. The first is conservatism in design of, and stringent quality control over components; the second is a requirement of protective devices and systems to detect and contain abnormal conditions; and the third is a requirement of backup systems. For a further discussion, see Environmental Statement, supra note 4, at 16-21.
. The emergency core cooling system is a combination of pipes, pumps, valves, tanks and other devices serving the function hereinafter described in text.
. Acceptance Criteria, supra note 7, at 20.
. See notes 14, 16, infra.
. The Commission’s regulations define “[l]oss of coolant accidents” as “those postulated accidents that result from the loss of reactor coolant at a rate in excess of the capability of the reactor coolant makeup system from breaks in the reactor coolant pressure boundary, up to and including a break equivilent in size to the double-ended rupture of the largest pipe of the reactor coolant system.” 10 C.F.R. tit. 50 app. A (1974).
. Id.
. A light-water cooled nuclear power reactor is one in which the core is cooled by ordinary light water, as distinguished from heavy water which contains atoms of deuterium instead of hydrogen.
. In its entirety, General Design Criterion 35 reads:
A system to provide abundant emergency core cooling shall be provided. The system safety function shall be to transfer heat from the reactor core following any loss of the reactor coolant at a rate such that (1) fuel and clad damage that could interfere with continued effective core cooling is prevented and (2) clad metal-water reaction is limited to neglegible amounts.
Suitable redundancy in components and features, and suitable interconnections, leak detection, isolation, and containment capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure.
10 C.F.R. § 50, App. A, 287, 292 (1974).
. Criteria for Emergency Core Cooling Systems for Light-Water Power Reactors, Interim Policy Statement, 36 Fed.Reg. 12247 (1971), hereinafter “Interim Policy Statement.” The Interim Policy Statement was corrected once, 36 Fed.Reg. 13105 (1971), and amended once, 36 Fed.Reg. 24082 (1971).
. The Interim Acceptance Criteria read as follows:
IV. A. Criteria for all light-water power reactors. These general requirements have been the basis of AEC safety review for some time. On the basis of today’s knowledge, the performance of the emergency core cooling system is judged to be acceptable if the calculated course of the loss-of-coolant accident is limited as follows:
1.The calculated maximum fuel element cladding temperature does not exceed 2,300° F. This limit has been chosen on the basis of available data on embrittlement and possible subsequent shattering of the cladding. The results of further detailed experiments could be the basis for future revision of this limit.
2. The amount of fuel element cladding that reacts chemically with water or steam does not exceed 1 percent of the total amount of cladding in the reactor.
3. The clad temperature transient is terminated at a time when the core geometry is still amenable to cooling, and before the cladding is so embrittled as to fail during or after quenching.
4. The core temperature is reduced and decay heat is removed for an extended period of time, as required by the long-lived radioactivity remaining in the core.
B. Criteria for specific reactors. Each reactor shall be evaluated in accordance with the general criteria of section IV.A., and using a suitable evaluation model. Examples of acceptable evaluation models are described in Appendix A. These evaluation models are acceptable to the Commission but their use is not mandatory. Other evaluation models may be proposed by applicants for review in individual cases.
36 Fed.Reg. at 12248 (Footnotes omitted).
. Id. The Interim Policy Statement invited interested persons to submit, within 60 days, written comments and suggestions for consideration “with the view to possible amendments.” Interim Policy Statement, supra note 15, 36 Fed.Reg. at 12250. The public was also informed that the Commission would “consider holding an informal public rule making hearing on this interim policy statement.” Id.
. Union of Concerned Scientists v. AEC, 163 U.S.App.D.C. 64, 75, 499 F.2d 1069, 1080 (1974). In addition to the interim criteria, the Interim Policy Statement also set forth “evaluation models” as prescriptions for acceptable emergency core cooling system designs. Interim Policy Statement, supra note 15, 36 Fed. Reg. at 12249-12250.
. See note 14, supra.
. See note 14, supra.
. Acceptance Criteria, supra note 7, at 1-2.
. Id. at 2.
. See note 4, supra. The formulation and circulation of this statement was required by the National Environmental Policy Act of 1969, Pub.L.No.91-190, 83 Stat. 852, 42 u’s.C. § 4321 et seq. (1970).
. Acceptance Criteria, supra note 7.
. Id. at 25-26.
. See note 7, supra.
. Nader v. Ray, 363 F.Supp. 946 (D.D.C.1973).
. Id. at 949.
. Id. at 955.
. Id. at 953.
. Id. at 954.
. Id. at 955.
. Counsel have agreed that the District Court’s decision has no res judicata or collateral estoppel effect in this case.
. Shutdown Petition, supra note 3.
. “The petition sought the same relief requested in Nader v. Ray, ‘based on the identical facts, the identical affidavits and the identical contentions. . . . ’” Id., quoting from the petition.
. The record before the Commission consisted in the shutdown petition, comments submitted by interested parties, and the entire record compiled in Nader v. Ray, supra note 27.
. Id.
. Id. at 23816.
. Id. at 23815.
. Id.
. Id.
. The Commission pointed out that the record in the rulemaking proceeding involved “months of hearings, over 22,000 pages of transcript, and thousands of pages of exhibits. ...” Id.
. Id. at 23815-23816.
. Quoting from an affidavit.
. Id. at 23816. The Commission stated further that “[r]esting upon an assumed (but impossible) standard of 100 percent assurance, petitioners build their case upon what they claim is the ‘undisputed inadequacy of the Interim Acceptance Criteria.’ But the [Interim Acceptance Criteria] can be viewed as ‘inadequate’ only if petitioners’ notion of absolute risklessness is accepted. We reject petitioners’ attempt to bootstrap their theory into a conclusion of inadequacy.” Id.
. Id.
. Id.
. Id.
. Id.
. The Atomic Energy Act confers the right to a hearing upon request in rulemaking proceedings. 42 U.S.C. § 2239(a) (1970). As stated in text, however, the shutdown petition did not request a hearing.
. See text supra at note 37.
. 10 C.F.R. § 2.802 (1974).
. 10 C.F.R. § 2.803 (1974). See also Siegel v. AEC, 130 U.S.App.D.C. 307, 314, 400 F.2d 778, 785 (1968).
. See, e. g., Administrative Procedure Act § 10(e)(B)(5), 5 U.S.C. § 706(2)(E) (1970); Universal Camera Corp. v. NLRB, 340 U.S. 474, 491, 71 S.Ct. 456, 466, 95 L.Ed. 456, 469 (1951).
. Administrative Procedure Act § 10(e)(B)(l), 5 U.S.C. § 706(2)(A) (1970).
. See note 14, supra, and accompanying text.
. See, e. g., Service v. Dulles, 354 U.S. 363, 77 S.Ct. 1152, 1 L.Ed.2d 1403 (1957); Vitarelli v. Seaton, 359 U.S. 535, 539, 79 S.Ct. 968, 972, 3 L.Ed.2d 1012, 1016-1017 (1959).
. WAIT Radio v. FCC, 135 U.S.App.D.C. 317, 320, 418 F.2d 1153, 1156 (1969), cert. denied, 409 U.S. 1027, 93 S.Ct. 461, 34 L.Ed.2d 321 (1972). Accord, Baltimore & O. R.R. v. Aberdeen & R. R.R., 393 U.S. 87, 92, 89 S.Ct. 280, 283, 21 L.Ed.2d 219, 224 (1968); USV Pharmaceutical Corp. v. Secretary of HEW, 151 U.S.App.D.C. 284, 290-291, 466 F.2d 455, 461-462 (1972); Environmental Defense Fund v. Ruckelshaus, 142 U.S.App.D.C. 74, 88, 439 F.2d 584, 598 (1971).
. Atomic Energy Act § 182(a), 42 U.S.C. § 2232(a) (1970).
. See Power Reactor Dev. Co. v. Electrical Workers Int’l, 367 U.S. 396, 406-416, 81 S.Ct. 1529, 1534-39, 6 L.Ed.2d 924, 931-936 (1961).
. Id.
. Id.
. Shutdown Petition, supra note 3, 36 Fed.Reg. at 23816.
. See, e. g„ 10 C.F.R. §§ 50.35(c), 50.40(a), 50.57(a)(III) (1974).
. 10 C.F.R. pt. 50, app. A at 288 (1974).
. Id.
. Interim Policy Statement, supra note 15.
. Id. at 12248.
. 10 C.F.R. pt. 50, app. A at 288 (1974).
. Id.
. Id.
. Shutdown Petition, supra note 3, 36 Fed.Reg. at 23815.
. See text supra at notes 15-18.
. See notes 14, 16, supra, and accompanying text.
. Acceptance Criteria, supra note 7, 36 Fed.Reg. at 12248.
. Shutdown Petition, supra note 3, 38 Fed.Reg. at 23815.
. In this court petitioners have not contended that the systems do not comply with the Acceptance Criteria. Indeed, they seemingly have proceeded on the basis that they do.
. See text supra at notes 15-20.
. See Part III, supra.
. See text supra at notes 59-63.
. Acceptance Criteria, supra note 7, 36 Fed.Reg. at 12248.
. Shutdown Petition, supra note 3.
. Id. at 23816.
. Id.
. Id.
. See text supra at note 80.
. See text supra at notes 47 — 49.
. Power Reactor Dev. Co. v. Electrical Workers Int’l, supra note 60, 367 U.S. at 408, 81 S.Ct. at 1535, 6 L.Ed.2d at 932. See also Crowther v. Seaborg, 312 F.Supp. 1205, 1234 (D.Colo.1970).
. See text supra at note 26.
. Red River Broadcasting Co. v. FCC, 69 App.D.C. 1, 5, 98 F.2d 282, 286, cert. denied, 305 U.S. 625, 59 S.Ct. 86, 83 L.Ed. 400 (1938). See also cases cited infra note 91.
. Id. See also Easton Utils. Comm’n v. AEC, 137 U.S.App.D.C. 359, 363, 424 F.2d 847, 851 (en banc 1970); Spanish Int’l Broadcasting Co. v. FCC, 128 U.S.App.D.C. 93, 105, 385 F.2d 615, 627 (1967).
. Red River Broadcasting Co. v. FCC, supra note 90, 69 App.D.C. at 5-6, 98 F.2d at 286-287.
. Gage v. AEC, 156 U.S.App.D.C. 231, 479 F.2d 1214 (1973).
. The Commission found that “the instant petition plainly makes no showing of good cause for petitioners’ belated participation in the [emergency core cooling system] proceeding.” Shutdown Petition, supra note 3, 38 Fed.Reg. at 23816 n. 4.
. Id. at 23816.
. Wellford v. Ruckelshaus, 142 U.S.App.D.C. 88, 91, 439 F.2d 598, 601 (1971).
. Friends of Earth v. AEC, 158 U.S.App.D.C. 252, 255, 485 F.2d 1031, 1034 (1973), quoting Nader v. FAA, 142 U.S.App.D.C. 264, 266, 440 F.2d 292, 294 (1971) (statement of Leventhal, J.). This standard of review is all the more fitting when “[w]e are not being asked to enjoin a Commission action, but to mandamus one.” Id.
. See note 36, supra.
. The Advisory Committee on Nuclear Reactor Safeguards is a body of nongovernmental experts convened for the purpose of advising the Commission on “the hazards of proposed or existing reactor facilities and the adequacy of proposed reactor safety standards.” Atomic Energy Act § 5, 42 U.S.C. § 2039 (1970).
. See text supra at notes 50-55.
. See text supra at notes 44-49.
. Supra note 60.
. 367 U.S. at 408, 81 S.Ct. at 1536, 6 L.Ed.2d at 932.
. For the reasons expressed herein, we also deny petitioners’ request to remand this case to the Commission for further consideration as to whether the impugned reactors comply with General Design Criterion 35.