ML19221A815
| ML19221A815 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0555, NUREG-0555-07.2, NUREG-555, NUREG-555-7.2, SRP-07.02, SRP-7.02, NUDOCS 7907090178 | |
| Download: ML19221A815 (6) | |
Text
Section 7.2 February 1979 ENVIRONMENTAL STANDARD REVIEW PLAN FOR ES SECTION 7.2 TRANSPORTATION ACCIDENTS REVIEW INPUTS Environmental Report Sections
- 7. 2 Trarsportation Accidents Involving Radioactivity Environmental Reviews 3.8 Transportation of Radioactive Materials 5,tandards and Guides Paragraph (g) of 10 CFR 6 51.20, ",^.pplicant's Environmental Report -
Construction Permit Stage."
" Environmental Survey of Transportation of Radioactive Materials to and f rom Nuclear Power Plants," WASH-1238, December 1972; Supplement I, NUREG-75/038, April 1975; and Supplement II, NUREG-0069, July 1976.
Other Responses to requests for additional information REVIEW OUTPUTS Environmental Statement Sections 7.2 Transportation Accidents Other Environmental Reviews None I.
PURPOSE AND SCOPE The purpose of this environmental standard review plan (ESRP) is to direct the staff's consideration and treatment of the assesar..ent of transportation accidents involving radioactive materials. The scope of the review directed by 109 040
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February 1]79 this plan will be governed by the level of compliance of the proposed project with the criteria provided in Paragraph (g) of 10 CFR g 51.20.
When the proposed project is in compiiance with this paragraph, the reviewer will conclude that these impacts 3re appropriately addressed through use of the " Accidents in Transport" section of Table S-4 of 10 CFR S 51. 20.
When the proposed project is not in compliance with this paragraph, the scope of the review will include a review and analysis of potential transportation accidents involving radioactive materials not considered in WASH-12Sa and Supplements 1 and 2, and a comparison of the environmenta's risks of these accidents with the data given in WASH-1238.
The review will also consider offsite transportation distances for spent fuel to determine if additional impact analysis (based on t.ransport distance) should be made.
II.
REQUIRED DATA AND INFORMATION The data and information required will be determined by the extent of compliance with Paragraph (g) of 10 CFR S 51.20, and by the nature of those proposed project details that may not comply with this paragraph.
A.
The following data will always be required:
1.
A statement from the reviewer for ES Section 3.8 to the effect that proposed transportation modes are in compliance with the provisions of Para-graph (g) of 10 CFR S 51.20 quoted in Section III of this ESRP; or when not in compliance, the nature and extent of those modes not in compliance with this provision (from ESRP 3.8).
2.
Estimated transporta ion distance from the plant to the facility to which spent fuel will most likely be sent (from ESRP 3.8).
B.
When the proposed transportation modes are not in compliance with the provisions or Paragraph (g) of 10 CFR S 51.20, the following data will be required:
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February 1979 1.
A description of each transportation mode that does not comply (from the ER).
2.
A description of transportation accident statistics for each of the above trcasportation modes (from the ER).
3.
Accident statistics for the transportation modes described in Para-graph (g) of 10 CFR S 51.20 (from WASH-1238).
4.
The environmental effects of the transportation accidents that could occur based on the proposed transportation modes and changes or additions to Table S-4 resulting from these potential accidents (from the ER).
III.
ANALYSIS PROCEDURE An analysis of transportation accidents will be made when the reviewer of ES Section 3.8 determines that the proposed project does not comply with the following provisions of Paragraph (g) of 30 CFR S 51.20:
Unirradiated fuel is shipped to the reactor by truck; irradiated fuel is shipped from the reactor by truck, rail or barge; and waste other than irradiated fuel is in the form of packaged solid wastes and is shipped from the reac-tor by truck or rail.
When transportation modes differing from these are proposed, the reviewer will prepare an analysis of these modes as they apply to the proposed transporta-tion of new fuel, irradiated fuel, and radioactive wastes.
The objective of this analysis is to determine whether the proposed transportation modes can result in environmental risks greater than those summarized in the " Accidents in Transport" section of Table S-4.
When it is obvious that the proposed modes do not represent an increased environmental risk, the analysis may be terminated and a statement prepared to the effect that the proposed transporta-tion modes are within the scope of Table S-4.
When this is not the case, the O
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February 1979 reviewer will consider the accident probabilities and accident statistics for each proposed transportation mode, will compare these data with the probabilities and statistics considered in WASH-1238 and Supplements, and will determine to what extent the dif ferences will af fect the accident data of Table S-4.
The impacts defined in Table S-4 include the impacts of transportation to a spent fuel reprocessing plant over a typical distance of 1600 km (1000 miles).
When the estimated transportation distance for offsite shipment of spent fuel (to a storage or disposal facility) exceeds this figure, the reviewer will con-sidar the need to analyze any additional impact resulting from this increased distance. The reviewer will consult with the NRC Environmental Project Manager to determine if additional supplements or revisions to WASH-1238 are available and will be guided by any such information.
IV.
EVALUATION When the proposed transportation of radioactive materials does not comply with the provisions of Paragraph (g) of 10 CFR g 51.20, the reviewer will deter-mine the extent to which transportation accidents involving radioactive materials represent an increased probability of risk to the general public over those risks shown in Table S-4, and will make a determination as to whether or not this increase is significant. Where the increased risk can be shown to be significant, the reviewer will evaluate the possibility of recommending use of those tran-sportation modes described in Paragraph (g) of 10 CFR g 51.20, and if it is nct possible to use these modes, will seek other alternative modes that project a lower risk.
The reviewer will ensure that estimated transportation distances for spent fuel have been considered in determining any increased probability of risks.
V.
INPUT TO THE ENVIRONMENTAL STATEMENT hhen the reviewer for ES Section 3.8 determines that the proposed tran-sportation of radioactive materials complies with the provisions of Para-graph (g) of 10 CFR g 51.20, the following statement will be made:
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The transportation of new fuel to the plant, of irradiated fuel from the reactor to a fuel rcorocessing plant,* and of solid radioactive waste from the reactor to burial grounds is within the scope of the AEC report entitled, Environ-mental Survey of Transportation of Radioactive Materials to and from Nuclear Fower Plants, dated December 1972.
The environmental risks of accidents in transportation are summarized in Table 7.2-1.
- Or to a storage or disposal f acility When an independent analysis of transportation accidents has been made the reviewer will prepare an input that:
(1) describes the proposed transpor-tation means and wFy they were proposed, (2) compares accident statistics for the proposed transportation modes with the statistics provided in WASH-1238, (3) discusses the increase in risk due to the proposed transportation modes, and (4) concludes that the risks are acceptable or that some alternative form of transportation is recommended for considerat an.
The reviewer is directed to the Transportation Accidents section of the Draf t Environmental Statement for Atlantic Generating Station Units 1 and 2 (Ref. i) for guidance in develop-ine this input to the environmental statement.
VI.
REFERENCES 1.
U.S. Nuclear Regulatory Commission, Revisea Draft Environmental Statement Related to Construction of Atlantic Generating Station Units 1 and 2, NUREG-0058 (Revision 1), October 1976.
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TABLE 7.2-1 ENVIRONMENTAL IMPACT OF TRANSPORTATION OF FUEL AND WASTE TO AND FROM ONE LIGHT-WATER-COOLED NUNEAR POWER REACTOR (a)
ACCIDENTS IN TRANSPORT Em ironmental Risk fD)
Radiological Effects Small Common (Nonradiological) Causes 1 fatal injury in 100 reactor years; 1 nonfatal injury in 10 reactor years; $476 property damage per reactor year.
(
Data supporting his table are given in the Commission's " Environmental Survey of Transportation of Radioactive Materials To and From Nuclear Power Plants," WASH-1238, "ecember 1972; Supplement I, NUREG-75/050, April 1975; and Supplement II, NUREG-0069, July 1976.
(b)Although the environrnental risk of radiological effects stemming from transportation accidents is currently incapable of being numerically quantified, the risk remains small regardless of whether it is being applied to a single reactor or a multireactor site.
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