ML19311C739

Public Watchdogs - NRC 2.206 Petition Exhibits 1-38 - Part 39

ML19311C739
Person / Time
Site:	San Onofre
Issue date:	09/23/2014
From:	Public Watchdogs
To:	Division of Decommissioning, Uranium Recovery and Waste Programs
Cruz Z
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Download: ML19311C739 (47)

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Q IDoris Mendlotos 1-30 PC Comments on NRCUDecormn. GEtS Supplement"* NUREG-0586 doc

3. The NRC risk assessment inappropriately ignores the population of children in its hurriedly raze structuresmsweep the radioactive mess under a porous and permeable "critical group" evaluation as the population most vulnerable to residual radioactivity carpet (or disperse the remains and cleanup materials In many unregulated forms far from exposure from decommissioning operations. This runs counter to NRC'S the reactor site), cut comers and add risks and contamination to an already precarious Organizational Value to a "Commitment ... to protecting the public health and safety."

clean-up operation. The public must be protected.

4. The NRC has a documented history of significant lapses in effective oversight of Our specific concerns are as follows: decommissioning operations as reported by the General Accounting Office in a May 1989 report, "NRC's Decommissioning Procedures and Criteria Need to be Relegation of More Decommissioning Processes to Generic Status Strengthened" (GAO/RCED-89-119). The GAO not only found that complete information does not exist for all licensed activities or buried wastes, but that NRC being CL-47/10 In establishing 80% (24 of 30) of the environmental impacts of decommissioning as was found to have terminated a license with radioactive contamination in excess of its "generic" the NRC is doing the industry's bidding to restrict or eliminate the affected own guidelines. Further, the report noted that NRC regulations lacked a time public's opportunities to comment on, guide, monitor and review the decommissioning of requirement for document retention. NRC's questionable past performance does not CL-47/11 nuclear power reactors in their communities. Regardless of any uniformity that may or support the agency's move toward generic treatment of decommissioning nuclear may not exist as issues to consider at decommissioning reactors - and our position is that facilities where affected communities are denied public review and full disclosure of any concerns of the relevant communities are site-specific - the NRC's move to make contamination, the decommissioning plan and license termination plan.

most considerations within the decommissioning process "generic" is a thinly veiled CL-47/12 project to eliminate public review and full disclosure through public hearings. Further, Rubbltzatlon this move runs counter to NRC'S "Openness" Principle of Good Regulation, wherein "Nuclear regulation is the public's business, and it must be transacted publicly and CL-47114 NRC'S proposal to allow "rubblization" (defined as: "the demolition of onsite concreteto candidly. The public must be informed about and have the opportunity to participate in structures. Rubblizing these structures could result in material ranging from gravels to the regulatory processes..." and to NRC's Organizational Value of "Service to the public, large concrete blocks, or a mixture of both.") of concrete structures at the reactor site to CA) and others who are affected by our work." (both found at httJnv/Aw.',e ovywho-we take place without opportunity for public intervention until after the action is completed ar/almhtirl)

CL-47/15 is outrageous. Rubblization poses some specific risks to the surrounding communities and the site workers, as the rubblized material could contaminate via air, soil. and water Arbitrary and Capricious Determination of"Levels of Significance" for pathways. Thus, Public Citizen insists that it is only appropriate that the affected Decommissioning Environmental Impacts communities surrounding the reactor site be given opportunities to review rubblizing plans and procedures, and that this issue be addressed on a site-specific basis.

CL-47/13 NRC's "Levels of Significance and Accountability of Environmental Impacts" assign values of risk to affected communities as "small," "moderate" and "large" as determinants Partial Site Release before License Termination for the denial or approval of a public site-specific review and, potentially, a public adjudication for environmental mitigation. Public Citizen maintains that these categories CL-47/16 The Supplement indicates that portions of a nuclear reactor site could be released from are excessively arbitrary and broad, and largely groundless for the following reasons: regulatory control prior to the site operator's license termination. This would relieve the nuclear utility of responsibility and liability for portions of sites (be they materials or real I. The biological effects of ionizing radiation are destructive. No safe "threshold level" for property) while still being licensed for the control of the entire site. Public Citizen is

- exposure to ionizing radiation exists for the general population (including the fetus). completely opposed to any such practice, which would allow radiationlradioactively contaminated materials and wastes to be released, reused, or recycled, without restnction,

2. Th1er isýalong history of unresolved regulatory conflict over radiation protection into the unregulated industrial, commercial, and public environment.

standards that are'utilized to determine NRC risk assessments. Federal regulators.

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including the NRC and the Environmental Protection Agency, have not reached a Externalizing Costs to Ratepayers/Taxpayers consensus on residual radiation criteria for decommissioning, with EPA standards being significantly lower (more protective) than NRC criteria. To our knowledge, this CL-47/17 Public Citizen is opposed to any policy that would shift the financial burden of conflict has not been resolved and, therefore, it appears that the NRC has unilaterally decommissioning to ratepayers. The cost of properly decommissioning (including 0)

, and arbitrarily concluded what standards would apply in determining whether a risk is thorough decontamination) a reactor site can vary widely, depending on the size of the cn "small," "moderate" or "large." facility, the amount of time in which it was operational, and the degree of contamination.

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- Dodri Mencdiola- 130 PC Cormenents on NRC'$ Decorum GElS Su ,meat.NUREG-0586 doe CD As the NRC itself stated in the Supplement, the lack of adequate decommissioning funds 3 can potentially result in delays and/or unsafe and improper decommissioning. Further, with utility deregulation and the attendant shuffling of corporate ownership, much uncertainty has developed regarding the ability of the owning and operating utilities to pay for proper decommissioning of their facilities. Public Citizen insists that site-specific reviews are necessary so that the public has an opportunity to ensure that the utility wilt be able to pay for the entire, thorough decommissioning process.

Relevance of "Out-of-Scope" Activities CL-47/18 There are several issues in the Supplement which are briefly addressed and dismissed as

".out-of-scope"which we insist need to be dealt with as site-specific issues for any thorough EIS on decommissioning, with full public rights to hearings, review, oversight, and disclosure maintained. "Ieseinclude:

1. Spent fuel storage and maintenance - The public at each reactor site community should determine how irradiatedl"spent" fuel is stored/dispositioned. If a centralized high level waste repository is opened at some future date to accommodate the irradiated fuel and high-level waste from a community's decommissioned reactor, the communities that exist along the possible transportation paths should also be involved in site-specific environmental impact reviews/assessments. To exclude spent fuel storage, maintenance, tranrsport. and disposal away from the reactor location from the scope of this GEIS/Supplemcnt, and the opportunity for site-specific EIS reviews, is arbitrary and capricious.

2. Low-level waste disposal at a a LLW site - The concept of rubblizing and capping a reactor site and allowing it to function as a low-level waste disposal facility without having the appropriate permitting and licensing hearing process is a serious departure from past NRC licensing practices, and any such "rubblizing" proposal should not be approved without a site-specific EIS review. To exclude this or any similar proposal from a site-specific EIS review, and the scope of this GEIS/Supplement, is arbitrary and capricious.

Please enter these comments into the public record.

Sincerely, David Rltter Policy Analyst Public Cituzen/Cntical Mass Energy and Environment Program Z

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Dale: 1/30102455PM Chief. Rules and Directives Branch Sublect: NIRS, WMEAC, DWM, CFNFGL Comments on DGEIS Supp I Division of Administrative Services Mailstop T 6 D 59 TO. NRC I II r United States Nuclear Regulatory Commission FROM' NIRS. WMEAC, DWM. CFNFGL Washington, DC 20555-000I RE. Comments on NRC Draft GElS Supplement Decommissioning of Nuclear Facilities NUREG 0588draft supp I Nuclear Information and Resource Service (NIRS)

Coalition for . Nuclear Free Great Lakes (CNFGL)

Don't Waste Michigan (DWM)

West Michigan Environmental Actlon Council (WMEAC)

Comments on Decomrmissioning GElS Supplement I To Whom It May Concern:

Pursuant to the Federal Register Notice ofNovember 9, 2001 on the availability of the draft supplement to the Final Generic Environmental Impact Statement on Decommissioning of Nuclear LI Facilities (NUREO-0586) for public comment, Nuclear Information and Resource Service, Coalition for a ri Nuclear Free Great Lakes and Don't Waste Michigan provide the following comments.

,')i 5-' CL-4811 NIRS reiterates and Incorporates our previous comments and fundamental disputes with regard to C

C,, the decommissioning GEIS as submitted in formal comments to NRC on July 1 1.13 and 14,2000. Our ,

Co organizations request that NRC include with this submission all of our organizations' previous comments on

.1 this and related rulemakings (including but not limited to the environmental procedures on BRC and those CL-48/2 that led to the development of 10 CFR 20 section E. the License Termination Rule). Our organizations continue to assert that NRC is deferring Its regulatory responsibility of radiological decommissioning to facilitate a cost driven utility self assessment through an expedited decommissioning licensing process and by restricting a duly promulgated public hearing process for affected communities as embodied under the CL-48/3 1988 law. We contend that decommissioning practices on nuclear facilities and its environmental impacts as major federal actions must be conducted under public review with full disclosure and documentation of the amount of radioactivity. the location of residual contarmnation and the types of radioactive contamination that remain on-site and off-site and are subject to site specific public hearings.

CL-48/4 The NRC claims the agency and the industry have accumulated substantial decommissioning experience and that this is justfication for hastening the genenc treatment of Environmental Impact Statements. In effect, this eliminates meaningful public involvement in site-specific reviews and prevents CL-4815 the necessary full disclosure of nuclear facility contamination and decommissioning practices. The fact is that decommissioning has a long and significantly checkered regulatory history. The draft supplement to NUREG-0586 does not address or acknowledge these repeated oversight failures including numerous decommissioning experiences where licensees did not adequately decontaminate their facilities These failures include but are not limited to:

Z the NRC does not know the types, amount and location of buried radioactive waste at some of its C decommissioned facilities;,

.many licensee decommissioning records are nonexistent or incomplete;.

G) -ground water contamination is higher than federal drinking water standards allow and 0

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-o -the long standing failure of the responsible federal regulatory agencies to prevent and prohibit radiation U1 contamination that can remain after the NRC terminates a nuclear facility license. (The Environmental

(.n 00 Protection Agency is on record requiring more protective cleanup levels than NRC, evidence that NRC's requirements are inadequate.)

P CL-48/6 These events do not warrant nor should they instill public confidence in staff conclusions that the agency and the industry can reasonably make the leap to the generic treatment of environmental impact CD statements for decommissioning nuclear facilities and effectively take away a community's review and the CD

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'a I) Radiological effluent pathways from nuclear facilities (water and air) must be included in the 2

CD full disclosure of the extent and location of radioactive contamination both on and off site. decommissioning analysis and mitigation plan.

CL-48/7 Our orgamzations are fully supportive of the permanent closure of nuclear power reactors. Our CL-48/13 Nuclear facility operation results in sigrificant offsite radiological contamination that is ignored decommissioning comments are not intended to dete or delay the soonest possible shut down of nuclear the beat of theirability under the current definition. For example., one known pathway occurs over the course of reactor operation CL-48/8 reactors. our goal is to require that nuclear facility owners and operators, to as the direct result of fuel rod degradation giving way to pin-hole leaks, cracks and loss of rod integrity with function as the good neighbors and responsible corporate citizens they claim to be. That would inclu.de fully radioactive contanunation to the reactor coolant system. Primary and secondary coolant piping leakage encapsulating and isolating all of the wastes and radioactively and chemically contaminated materials results in radioactive contamination releases being deposited and accumulated as sediment on river and resulting from their operations and decommisslonlng. It Includes doing everything possible to:

lakebed$ and coastal receiving waters from deteriorated reactor coolant discharge systems. Thi is of I) Prevent public exposures in the current and future generations to radiation and celnUcals from nuclear particularly more concern for utilities that operated once-through cooling systems and/or boiling water power production, waste management, aransportation. "clean up" and decommirssioning.

2) Prevent additional environcental rontamination both on-site and off-site and to remediate and reactor technology though not exclusively so. Some of our organizations are aware that reactor operators, as inuimize that which has already occurred*. in one case of the Big Rock Point nuclear generating station, have argued that offiite radioactive sediment radioactive wastes Decommissioning areas should not be disturbed by ranoval/decontamnmation efforts and are better left alone than CL-48/9 3) Paying the full costs for long-team monitoring and isolation of decontaminatd The dconumssiomng definition does not require the utility to analyze the scope of this should not end up as a new set of publac subsuides for nuclear power by allowing the long term costs (economic, health, resource, etc.) to be denied. ignored or defined away by NRC with no offitte contamunation, consider its cleanup nor effectively regulate the enforcement of decontamination of recourse for the local community or at and federal taxpayers that will end up with the costs by residual radioactivity that has =mgrated from the reactor site and accumulated off site in affected default. commuiuties resources such as fresh water supphes. ThesI advertent releases of radioactivity as the result of station operation need be covered within the scope and disclosure as environmental impacts within the CL.4a10 Inerlent in the decision to operate the reactors is an acceptance on the part of the generator and the decommissioning process.

re1gulatr of the production of long-lastng radioactive waste a&d radioactive and chemical contamination of large volumes of resources, Decommissioning should include responsibly managing that material, not NRC in its evaluation of the environmental impacts acknowledges "Levels of radionuclide denying its existence. emissions from facilities undergoing decommissioning decreased, because the major sources generating "P emissions in gaseous and liquid effluents are absent in facilities that have been shut down." Consequently.

(0 the NRC currently only considers radiological effluent impacts as a result of decommissioning operations

0) while ignoring the potential need for nutigaton of cumulative and persistent toxic radioactive materials deposited downstream over the decades of operation of a reactor.

The Comnission's Definition of Decommissioning is Fundamentally Flawed and LUnmted In Scope CL-48114 2) The contamination of soil, land and property beyond the station boundary line must be included in the CL-48/11 Our organizations have a fundamental dispute with the Commission's definition of decommiussonig analysis and plan.

decomsissioning. The NRC currently defines decommissioning as "to remove a facility or site safely from Offsitte migration of radioactive materials has occurred through both deliberate and Inadvertent service and reduce residual radioactivity to a level that permits (1) Release of the property for unresicted removal of materials originally contaminated onsite (tools, concrete construction blocks. etoc) For examplc.

use and termination of the license; or (2) Release of the property under restricted conditions and termination concrete cnderblocks used to construct a shield wall at the Connecticut Yanrkee's Haddam Neck nuclear of the license." power atation were inappropriately distributed to affected communities as construction materials for buildings including a children's daycare famlity. We believe the Connecticut Yankee incident is not an Decommissioning should not permit the release of radioactive contamination from regulatory isolated case. The scope of the current definition does not provide for the investigation, analysis and control and the control of some identified responsible party. At public meetungs (in 1993 and in 2001) mitigation of radioactive materials, equipment and components originating from a nuclear facility that have across the country on the issue of "clean-up," the public consistently called for continued regulatory control been deliberately or inadvertently rekased to affected communities.

over any and all wastes, materials, properties and sites with contarmnation from nuclear power and weapons fuel chain activities. Rather than requiring the identification, capture and isolation of the remains of nuclear CL-48/15 3) The historic undocumented burial of nuclear waste onsite at nuclear power stations must be investigated, power operations, NRC is legalizing the release of contamunated sites, properties, materials and natural surveyed and mitigated by station owners under the deconiussiomng plan resources. By segmenting the portions of the decommissioning process into separate Environmental Impact As the United States General Accounting Office (GAO) May 1989 "NRC's Decommissioning Statements and supplements, the public is prevented from addressing the amount and method of identifying Procedures and Criteria Need to Be Strengthened" (GAO/RCED-89-1 19) reports in Its Executive Summary.

residual contanunation of the environment, natural resources, the community and downstream and downwind ecosystems. The public is prevented from addressing and preventing the concept of allowable "For almost 25 years. NRC allowed licensees to bury radioactive waste on-site without prior NRC approval.

doses to the public from nuclear power operation, wastes and decommissioning activities. We protest the NRC required the licensees to retain records on the amounts and substance buried rather than provide them designation of issues related to allowable contamunation levels and doses being deemed "out of the scope" to NRC. In five of the eight case GAO reviewed, licensees buried waste onsite, but four licensees either of this document. dtd not keep disposal data or the data are Incomplete. In one case, NRC terminated a license and 10 years later learned that radioactive material had been buried on the site. Also. NRC generally does not require NRC *gnores "offsite" radiation exosure licensees to monitor for groundwater or soil contamnation from buried waste.

All five licensees have found ground water contamunated with radioactive substances. At four sates, some z This agency's definition of "decomnussionmg" is fundamentally flawed in limiting its scope of of the contamination appears to have resulted from the buried waste CL-48/12 "property" to the site boundaries. The NRC scope needs to be broadened to encompass the decontamination the contanination at one site was 400 times higher than EPA's drnking water standards allow. At another CD or mitigation of"property" in addition to strictres, systems and components of the nuclear power station site, the contamanation was 730 times higher, but the source was not known."

that exist beyond the fence line that have been contaminated none the less as a direct result of station CD operation.

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1 Commetsrrsttigp ftuat doc. Page 4 [DorisMendila - NRC Deconmesloning GElS Supp 1 Comment multtgp final doc Dods Medlola-NRC Decomrnaaonlng G*lS'SU transfers and mergers "were not always rigorous enough to ensure that decominssiomng funds would be and materials from,,

CL48/16 4) An Inventory of all the radioactivity, radioactive wastes adequate. Moreover. NRC did not always adequately verify the new owners' financial qualifications to reactor operation and decommissioning, and Independently verified reporting of its disposition (whether safely own and operate the plants."

onsite or offsite, whether In licensed or unlicensed facilities and specifics of its storage condition) should be a required part of the environmental review and reports. This Information must be part of the site-specific Environmental Impact Statement process and fully disclosed at each reactor as site.specific Issues, with the CL-48/24 The Yankee Rowe nuclear power station is a clear example of the inability to accurately assess the final cost of deconusdsslosin& Originally decommlssioning estimates ran under $100 million dollars while opportunity for formal local hearings and legally- binding Input. The corporations responsible for the the current expenditures are estimated to be just under $500 smallion for the small 170 megawatt pressurized radioactive wastes from nuclear power reactor operations should be required, by NRC, to keep balance water reactor.

sheets of the radioactivity generated by their reactors and the decommissioning process, and track the The Shoreham nuclear power station can not be relied upon as an accurate gauge for decommlssioning costs disposition of that radioactivity whether It is kept onsite. allowed to leak out into the air and water, or as it never reached full power operation.

shipped to licensed or unlicensed facilities for disposal or processing, and for possible release into household items. NRC SEEKS TO LIMIT PUBLIC REVIEW AND HEARINGS BY ESTABLISHING ARBITRARY "LEVELS OF SIGNIFICANCEE" ON DECOMMISSIONING ENVIRONMENTAL IMPACTS CL-48117 We oppose any unlicensed disposition of long-lasthng radioactivity from the nuclear fuel chain activities As long as radioactive materials remain, someone should retain a license for those materials, and responsibility We have a fundamental dispute with the NRC effort to eliminate public review and full for themn. That burden should not be shifted to the states and local comnunitides without clear CL48/25 disldosure through public hearings on dec* ianssaoning practices and mitigating environmental acknowledgement of the stewardship responsibility for that material. impacts based on arbitrary and capricious categories for determining "generic" and "site specific" proceedings for nuclear power station deconmissioning.

• CL-48/18 NRC AND INDUSTRY FAILURE TO RELIABLY ESTIMATE THE REAL COST OF CL-48/26 NRCs "Levels of Significance and Accountability of Environmental Impacts" assign values DECOMMISSIONING AND REASONABLY ASSURETHE AVAILABILITY OF ADEQUATE of rnsu to affected comunnities as 'small," "moderate" and "large" as thresholds for denying or DECOMMISSIONING FUNDS DOES NOT JUSTIFY OR SUPPORT GENERIC TREATMENT OF conducting a public site.specific review and potentially a public adjudication for environmental

.-u ENVIRONMENTAL IMPACT STATEMENTS mitigation. Our organulzatIons argue that these broad categories established by NRC are largely CD baseless for the following reasonaa

"-4 "The NRC GEIS does not adequately address the historic inability by the NRC and industry to accurately assess the final and actual costs associated with decommissioning and the associated 1. The biological effects of radiation are deleterious. No safe threshold for radiation exposure for the underestimation of the rate of accrual for funds set-aside by electrical utilities. The final cost for general population (including the developing fetus) has been established.

decommissioning remrains highly speculative and therefore likely to continue to be significandy underestimated. As NRC has stated in the DGEIS Supplement the unavailability of adequate 2. There is along history of unresolved regulatory conflict over radiation protection standards assumed to decommissioning funds potentially can result in delays and/or unsafe and improper decommissioning. determine NRC risk assessments. Both federal and state agencies have sought to provide greater protection Therefore, our organizations contend that site specific reviews are necessary for public review and than NRC requires. In addidon. NRC disclosure of the avallability of adequate decommissionlng funds assigned to an adopted decommissioning plan 3. The NRC risk assessment inappropriately ignores the population of children in its "critical group" evaluation as the population most vulnerable to residual radioactivity exposure from decommissioning and the operations. ,

CL-48119g While the Executive Summary of NUREG-0586 Supplement I claims that the NRC Industry have over 300 years of decommissioning experience with 22 nuclear reactor facilities permanently shut down, the fact remains that the process Is still relatively new and NRC has yet to complete asingle 4. There is a documented history of significant lapses in effective NRC oversight of decommissioning operations as reported by The General Accounting Office In May 1989 "NRC's Decommissioning radiological decommissioning operation to alicense terrinatIon plan for a typical large U.S. commercial Procedures and Criteria Need to Be Strengthened" (GAO/RCED-89-119). The GAO not only found that reactor that operated for any significant length of time. As stated by Mr. Michael Masnick with the NRC at complete Information does not exist for all licensed activities or buried wastes. but additionally that NRC the Public Scoping Meeting on Intent to Prepare Draft Supplement To Generic Environmental Impact was found to have terminated a license with contamination in excess of its guidelines and NRC regulations Statement on Decormissioning of Nuclear Facilities in Boston, Massachusetts, May 17.2000 with regard lacked a time requirement for document retention. NRC's checkered history does not provide justification z to a question on how many license termination plans have been accepted by NRC. he responded, "none for the agency to move forward with generic treatment of decommissioning nuclear facilities where affected CL.48/20 have resulted in a license terinatidon." It therefore appears that 300 years of decommissioning experience communities are denied public review and full disclosure of contaminatlon, the decommissioning plan and without a single license termination plan approval does not suggest that NRC Is prepared to treat the issue m of cost to adequately decounission generically.

Cn 0 CL-48/21 The cost of decommassiornng nuclear facilities can vary according to the size of the facility and the THE DECOMMISSIONING ALTERNATIVES DO NOT WARRANT GENERIC TREATMENT THE degree of contamination. As aresult of electric utility deregulation where acompetitive market has ENVIRONMENTAL IMPACT STATEMENT AND ARE THEREFORE SUBJECT TO SITE SPECIFIC CL-48/22 replaced regulated rates, traditional methods of amassing decommissioning funds through imbedded utility PROCEEDINGS ci, CL-48/23 rates have been replaced with by competitive electricity rates. Additionally, ownership of nuclear facilities CD has changed for more than half of the nuclear power plants In the United States through mergers and , CL-48/27 Alternative methods being considered by the NRC Include "entombment" and

'0 transferS. This shuffling of ownership has raised much uncertainty about the availability of adequate funds "rubblizatlon." These Involve leaving more nuclear waste on-site in an effort to reduce Industry's

01) for the eventual decommissioning of the nuclear facilities. short-term decommissionlng costs but are likely to Increase long term costs to affected communities As reported by GAO December 2001 "NRC's Assurances of Decommissioning Funding During once the sites are abandoned after license termination. The proposed alternative methods CD Utility Restructuring Could Be Improved" NRC reviews of financial arrangements exchanged In these r -,,ý

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CD slipping low-level radioactive wastes from decomnmissioning sites to disposal sites. Although NRC has additionally ramse significant technical and environmental impact issues and conflicts with the estimated that rubblizatlon could save a licensee from $10 million to $16 million in waste disposal permanent emplacement of so-called "low-level" radioactive waste at nuclear facility sites not costs dunng decommissioning, Its Advisory Committee on Nuclear Waste has concluded that originally licensed as regulated nuclear waste management facilities. The proposed alternative technical factors, such as the depth of radioactive contamination and the volume of rubblized waste, methods are tantamount to creating an unlicensed radioactive waste disposal site. These alternative could significantly dindnish the potential cost savings. The Advisory Committee also believes that methods must therefore be subject to review by the affected communities with full disclosure and evaluating radioactive material content and doses from rubbhzathon, both at the site and In local documentation of the amount of radioactivity, the location and condition of all residual groundwater, may prove difficult and expensive."

and off-site contamination and the types of radioactive contamination that remain on-site. On-site contamination and radioactivity and associated issues Involved with extended Institutional control CL-48/32 -The NRC staff's decision that entombment might reduce decommissioning costs is questionable",

must all be subject to site-speallc public hearings. "According to NRC's staff, 'very expensive remedies' could be required if an entombment The NRC effort to approve alternate decomnuiasioaing methods constitutes significant configuration proved unable to adequately Isolate radioactive contaminants over the 100-year or CL-48128 uncertainty and an impediment to accurately estimate the real cost of decommsssoning nuclear longer (up to 300-yearn by NRC projectionsl tiem period needed for radioactive decay. Given the facilities. There is no real assurance that adequate funds will be available to safely and properly length of time Involved, states are concerned that they will have to pay remediabon costs should an and Co deconmuasion the site and provide for remehdation of all necessary cleanup. These regulatory entombment faiL" environmental issues do not support generic treatment of environmental impact statements. In fact CL-48/33 "Aside from questionable cost benefits. rubbllzation and entombment raise a number of because of the economic and technical and environmental uncertainties of the Rubblizatlos and technical issues. For Instance, NRC does Dot Intend to require that sites where rubblized radioactive Entombment options, they shumld be subject to much more rigorous review than provided by this materials would be buried have protection equivalent to off-site disposal facilities for low-level Supplement. This Supplement gives only cursory attention and unsubstantiated dismissal of radioactive waste. Disposal facilities for commercial low-level radioactive waste, which are licensed potentially very serious environmental consequences of the Rubblization, Entombment and Partial and regulated by NRC oar by state (under agreement with NRC), must be designed constructed, and site reltese options. operated according to NRC regulations (or compatible regulations issued by the host state). In addition, to obtain a license to build and operate a disposal facility, the prospedive licensee must The Entombment alternative characterize the facility site and analyze how the facility wil perform for thousands of years.

As a decomrmissioniog option, entombment provides for the uuhty to remove the irradiated fuel However, according to NRC, a rubblized site is not comparable to a low-level radioactive waste from the core for disposition through either on-site dry cask storage or away-from-reactor Interim storage disposal facility... Nevertheless, 10 CFR Part 61 does not differentiate between what does or does Once the fuel is removed, the facility is allowed to radioactively decay for a specified period of time up to not qualify as a low-level waste disposal action or facility on the bass of the quantity, forms, or range 300 years before demoution and site clean up Is achueved. of the low-level radioactive waste to be buriedl" radioactive waste disposal sites CL-48/34 "Water intrusion is also a major concern for rubbLhzd or entombed sites, and the fact that Z

Rubblization as an alternative to acesed most nuclear power plants are situtated In shallow water table or flood plan locations may limit the Rubblization Is described as the partial decontamination and demolition of radioactively viability of these options."

CD contaminated buildings at nuclear power stations. The interior concrete surfaces are only partially decontamnnated and the entire structure (concreteg steel re-enforcement bar and other materlais) is

-s cap. CL-48/35 The above reasons illustrate the lack of a sound basis for staf conclusions that the then razed to grade level into the foundation hale. The burial site Is then covered over with soil decommissioning alternatives of entombment and rubblization are of "mince" environment impact NRC and industry are also proposing that rubblized contaminated material can be hauled to landfills and can be treated generically to avoid public review and full disdolsre in formal public hearings.

unlicensed for radioactive waste. We therefore adamantly oppose such generic treatment.

CL-48/29 However, the rubblization process must account for the permeation of porous concrete structures (containment dome, basemat, and walls) with radioactivity much deeper that surface contamination that would be sand blasted during a decontamination proceass. Activated concrete would be rubblized and would thus constitute so-called "low level" radioactive waste. Long-lasting Overall concerns:

3 radioactive elements such as cessum-1 S and strontium-90 are present with many other fission NIRS and numerous other organizations and local community groups have concerns with the products and radioisotopes In the concrete and should not be Ignored or defined away. No data are following overall effects of this Supplement:

provided In this Supplement to justify RubbUlation and on-site or off-site disposition. Thus, local 7:1 communities have every right to participate legally Cm adjudicatory proceedings) and be provided with Information- full disclosure of such planning. CL-48/36 NRC allows "evibblization' (crunbling the concrete reactor building) of nuclear reactors, without opportunity for public intencvetion unul the action is completed.

radioactive CL-48/30 Essentially, the agency and industry are proposing that a so-called "low-level" waste dump can now be grandfathered on a reactor site without a formal permitting and licensing CL-48/37 NRC allows portions of sites to be "released" from regulatory control before the whole site it released hearing process. The decommissioning utilities wall provide an analysis that can "assure" that no ground water movement will occur through the radioactive burial site providing a potential CL-48/38 NRC opens up two "entombrment" options.

The utilities transport mechanism and potential radioactive exposure to the public and envrounmenL CL-48/39 NRC ignoses radiation dangers after decommissioomng is done and utility is relieved of liability.

will pose are to provide a "dose model" to "assure" the affected communities that the radioactive site no health risks to present and future public health and the environment. These "assurances" cannot be bona ride by generic treatment and therefore require the availability of site specific proceedings. CL-48140 NRC Ignores radiation exposures to children and other vulnerable irembers of the populaUon and creates a "NRC's Assurances of fictitious highest exposed "cntical group" based on unsubstantiated assumptions.

CL-48/31 We concur with the GAO rindiags as reported in CAO-02-48 2001.

Decommissloning Funding During Utility Restructuring Could be Improved" dated December GAO reported the following conclusions: CL-48141 NRC ignores radiation offsate and per*its utiliues to ignore it In decommissioning planning. NIPMcalls on the NRC to incorporate offsite contamination into all evaluations of covironntenial impacts.

"Rubblization represents a departure from NRC's past licensing practice, which emphasized

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from applying to most of the deconusmssioning Holland, Michigan 49423 CL-48/42 NRC prevents the National Environmental Policy ActSupplement I satisfies the Environmental Policy Act that this proposed process. (The claim appears to beissues for most of the decommissioning )

Thomas Leonard, Executive Director West Michigan Environmental Action Council CL-48143 NRC cleverly makes most aspects of decorrunissioning -genersc" rather than stte-specific, so they cannot be legally reviewed or challenged at individual sites. 1514 Wealthy Street SE Suite 280 Grand Rapids, Michigan 49506 unsafe CL-4 8144 NRC redefines terms to avoid local, site specific opportunity to question, challenge and prevent decommissioning decslons.

impact categories for each CL-48145 NRC sets arbitrary and unsubstantiated (low, medium and high) environmental effects, to justify not fully of the steps in decommissioning. to give the appearance that they have minimal addressing them now and to prevent their inclusion in site-specific analysis.

operating CL-48/46 NRC is removing the reqsrernent for a license amendment when changing from a nuclear power license to a nuclear materials possession-only license. (With no license amendment, there is no opportunity for public challenge or adjudicatory processes )

CL-48147 NRC is attempting, with this supplement, to legally justify the removal ofthe existing opportunities for community involvement and for legal public Intervention until alfer the bulk of the decommissioning has been completed.Mhis Includes such activities as flushing, cutting, hauling and possibly ribblizing of the reactor.

(0 (D CL-48/48 NRC states that the portion of the decommissloning regulations (10 CFR 20 section E and its Environmental Impact Statement, NUREG 1496) that set the 25. 100 and 500 millirems per year allowable public dose levels from closed, decommissioned nuclear power sites, are not pant of the scope of this Supplement CL-48/49 NRC defines decommissioning, in part. to include the "release of property for unrestricted use...." and the "release of property under restricted conditions..."

NMRSstands firnmly against the "release" of radioactively contaminated materials into daily consumer use and commerce or unregulated disposal Respectfully submitted, Paul Gunter, Reactor Watchdog Project Nuclear Information and Resource Service 1424 16's Street NW Suite 404 Z Washington, DC 20036 C 202 328-0002 ext 18 rTi Michael Keegan G) Coalition for a Nuclear Free Great Lakes 63 811 Harrison Street (21 Monroe, Michigan 48161 00 C/)

C Alice Hirt "Don't Waste Michigan

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Date: 1/31102 223AM

Subject:

Comments on Decommissioning Nuclear Power Reactors Environmentallmpact Statement I am very concemed that children, who are much more susceptible to the /,/O (/]* I CL-4911 effects of radiation, may not be being looked at inthe Environmental Impact StalemenL This is a very serious Issue. & if left unaddressed, would not 4 4 Fl..-- /

only be morally wrong, but could lead to a horrible name In history for the NRC, & possibly legal action.

CL-49/2 I am hopeful that you will act in the interest of the public, & listen to the concems of all of the communities that will be affected by the by-products of nuclear energy. Offsite radiation is something that must not be Ignored.

Thank you for looking into this.

Eileen Greene 3580 Honeycomb Rd -,

Salt Lake City, UT84121

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413-339-5781 cansnukebusters org AWARENESS N ETWORK January 30. 2002 Chief, Rules and Directives Branch Division of Administrative Services Mail Stop T-6 D59 U.S. Nuclear Regulatory Commission Washington. DC 20555 C,

ta. RE. Generic Environmental Impact Statement on Decommissioning Nuclear Facilities: Draft Supplement "U ,~

I Dealing with Decommissioning of Nuclear Power Reactors Deair Sir or Madam:

By this letter, the Citizens Awareness Network (CAN) formally submits written comment on the draft supplementl Generic Environmental Impact Statement (GELS) involving the decommissioning of nuclear reactors. CAN provided the Nuclear Regulatory Commission (NRC) with verbal comment at the draft supplemental GELS scoping meeting held in Boston, MA on May 17, 2000 and written comments in July 15, 2000. CAN is a volunteer, grassroots organization with chapters in reactor communities in MA, CT, VT and NY. We have over 3,300 members and represent the views of many thousands more. We attempted to email these comments on 1/30/02. but were unable due to server problems.

CL-50/1 NRC. The court ruled that The regulations are in violation of the appellate court decision In CAN vEnvironmental decommissioning remained a "major federal action" requiring National Policy Act (NEPA) compliance. CAN strongly urges the NRC to enforce NEPA compliance and require decommissioning CL-50/2 reactors to undertake site specific Environmental Impact Statements (EIS). In addition CAN requests the Commission withdraw the proposed draft and revise it so that it complies with the ruling of the court decision. Until such a time when site specific EIS's are done, CAN requests that paragraphs below be incorporated into the draft supplement I GELS.

z CL-50/3 The Appellate Court justices opined that your agency was in violation of its own regulations and Rulemaking M

m process in approving the experimental decommissioning at the Rowe reactor without a decommissioning plan and an environmental assessment. In addition, the court has ruled that decommissioning is a major federal 01 action and requirs NEPA compliance. "An agency can not skirt NEPA or other statutory commands by "Aýý2s ý 9> exempting a licensee from compulsory compliance, and then simply labeling its decision "mere oversight" co rather than a major federal action. To do so is manifestly arbitrary and capricious." We believe NEPA C-n

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2. New environmental assessment been found to be inaccurate both on and offsisl.

actual testing substitute for an individual EIS. as computer modeling can not substtute for as a major federal action. As the sites, few large-scale CAN believes it is essential for NRC to conunue to define decomnussioting CL-50/1 2 3. Although the NRC claims numerous successful decommissionings of nuclear Decommissioning CL-50/4 an action which, even under the reactors that operated for decades have completed successful decommissioning Appellate Court opined '..._ it is undisputed that decommissioning is have been routinely Commission's new policy, requires NEPA compliance 10C.F.R S 51.95(b,)*

CAN believes that streamlining remains experimental. Resources and time required for decommissioning a site CL-50/5 abdicates the responsibility to underesutmated. More importantly, worker doses have been repeatedly underestmated.

Safe the process for nuclear corporations and setting aside NRC requirements the workers. Nuclear protect the health and safety of the workers, the public, the environment, and violates citizen due process. decommissioning is about radiological control and the need to limit exposures to by the NRC, to regulate thenselves, which this corporations have failed to do this because of inexperience and a lack of enforcement Nuclear power generators should not be given broad discretionary powers decommissioning Draft proposes. Protecting public and worker health and safety and the envsronment must remain the NRC With over 100 nuclear reactors yet to be decommissioned in this country, cutting workforce exposures by nussion. exposures by 200-300 person-remin per reactor will reduce the nation's nuclear 20.000-30,000 person-rem.

and cessation and that the CL-50/6 Can requests the NRC restore distinct categories between reactor operations Possession Only Ucoense should be reinstated. It affords citizens the possibility for a hearing prior to reactor CL-50/13 4. Nuclear reactors, through planned and unplanned radioactive releases, can create plumes ofsprings, reached decommissioning. The opportunity for a hearing must not be withdrawn by the Commission.

The hearing is contaminaton, which migrate offeite, Yankee Rowe currently has a plume, which offer a hearing at the feeding into the Deerfield River where residents recreate. Connecticut Yankee has plumes of truum essential for communities to participate in matters that vitally effect them To River for decades.

termunation of the license rather thm at the cesation of operations sets aside meaningful citizen participation. and other radionuclides which have migrated into the aquifer and the Connecticut that have Accountability (i e. remnediation and/or long term monitoring) for plumes of contamination Shutdown Decommissioning offsite consequences must be established. Furthermore, accountability must be established for routine CL-50/7 Major component removal should not be approved with the submission of a Post CL-50/14 Rock Point,

"-p Activities Report (PSDAR), A clear definition must be established to clarify what constitutes major and minor NRC-regulated releases, which have accumulated in the discharge pathways Big by such releases removal. Approval of decommnssiomng plan should be required before major decommissioning Millstone Unit 3 and other reactors have identified contaminated sediment caused N component the decommissioning Remedtation must capture such plumes both onsite and off.

acuvities begin The PSDAR does not afford the community effective input into activities planned by the licensee. The process since this document is a skeletal outline of generalized sub part L further inhibits public tools, soils, CL-50/8 ehlmination of sub part M hearings coupled with the insuting of CL-50/15 5. Methodology must be established to locate and collect for proper disposal contaminated offWite by workers section 189a of the Atonuc concrete blocks, plywood and other building materials that may have been taken participation and is a violation of citizens constitutional tights guaranteed under Rowe.

Energy AcL during reactor operation such as was the case at Connecticut Yankee and Yankee participation. The PSDAR does not CL-50/16 exposure calculations must capture and include

6. In addition to onsite worker doses, decommissioning decommaisioning CL-50/9 The PSDAR skirts accountability and obstructs required public can understand what will be taking doses incurred by workers involved in offiste reactor activities i.e. shipping, require a clear description of the methodologies so that the public decontamination, smelting, recycling etc. of all radioactive materials and components.

can the public meaningfully place during decommissioning Only with a sufficiently detailed plan, to the decommissioning research, investigate, formulate comments and quesuons, and possible objections calculations in site release necessary given the CL-50/17 7. Using an adult male as the average member of the critical populauon for dose activimes. A meeung does not afford cizens the level of institutional accountability meetings, as criteria does not establish effective clean-up standards. The adult male assumptions address workers dangers of enviro-toxic contamination inherent in the reactor cessation Informational use the 'average obfuscated, confused, and dunng reactor operation, however when reactor sites are released for unrestricted experienced at Yankee Rowe, Cr Yankee, Maine Yankee., and Millstone Unit I the greatest Court chastised member" of the critical population reqmis the inclusion of children since they bear ignored the concerns of local citizens. Both the Federal District Court and the Appellate of Ionizing Radiation regulatory recourse save one burden of the affects of ionizing radiation as described in the Biological Effects the agency for this approach. If the community has concerns, and there is no (BEIR) V report.

"meeting" with NRC, the Commission will, in fact, create polarization between the community and regulator leading to erosion of public confidence in the NRC CL-50/18 8. The Ucense Termination Planbegins. (LTP) should be established, reviewed by the public and approved by the NRC before site renediation Further Comments:

use should not be allowed unul the LTP has been established, and taken into conssder-aton when CL-50/19 9. Partial release of property for unrestricted CL-50/10 I. Health problems in the community must be determined radiation through routine reviewed by the public, approved by the NRC and implemented on the given piece of land.

decommissioning plans are being established since continued exposure to Furthermore, methodology should be established for preventing recontamination of the released jeopardiz the health and decomrmissioning releases and the inadvertent release of hot particles can safety of the public.

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CD Dta endifotaa CAs omments GEtSsuppiement decommlsslntfngreactors 102 do" Page 5 Mendta - CANs comments GEtSsupplemen decommlsslonmg reactors 102.doe Df~ons Page 4 4 Mimi A-,mNm~or 5 kLw,.A ro I*rNd.sI- C..ws..D..t.Awpin... I ,fAe e*m. Dcodnlogm8Rsxtrw address the serious problem of locating and remediating underground contamination. Before 1980, the property through environmental migration e g. rain, wind, etc and future decommissioning activities NRC in fact allowed the burial of rad waste onsite. A General Accounting Office (GAO) investigation i a excavating, tracking or relocating contaminated materials. found that the routine burial of rad waste 4 feet deep at reactor sites before 1980 occurred without particles. Yankee adequate documentation.

CL-50/20 11. Clear methodologies should be established for the clean up of transuranics and hot Rowe failed to include transiranic meaumrements in Its LIP and currently Connecticut Yankee intends protocols by the to avoid doing direct alphi measurements (and beta measurements) through less expensive surrogate CL-50/27 19. Each reactor community should have representatives trained in MARSSIM and other NRC so that they can effectively comment and express their concerns about the adequacy of the measurements of easier-to-detect radionuclides through less expensive surrogate measurements of procedures being used.

easier-to-detect radionuclides. Surrogate measurementa must not be allowed at sites where consistent ratios of radionuclides do not exist. CL-50/28 20 In the aftermath of September 1 *. NRC and licensees must address earlier assumptions that CL-50/21 12. The burial of radioactively contaminated material as a means of site remediationIs unacceptable for decommissioning was less dangerous than operation and that security measures and insurance could property that is to be released for unrestricted use. Rubblizatlon (the burial of contaminated rubble) be reduced because of it. Nuclear fuels pools as well as on site dry cask storage of high level waste must not be permitted under any circumstances. The permission to build nuclear reactors hinged upon are targets for terrorism. In fact decommissioned sites could be selected as targets because there is the utilities' commitments to regulators and the community to restore the site to *green fields".

less secunrty and oversight dunng decommissioning and the monitoring of the ISFSL NRC must Rubblization is a blatant default on cleanup commitments, is a gross injustice to reactor communities required Increased security and the reinstatement of Insurance provisions. Additionally, emergency and is a regulatory cave-in to utilihies' desires and financial needs. In response to nhiblization CAN preparedness drills and the EPZ should be reestablished. KI should be stockpiled in communities since also incorporates by reference Contention's 5 2 and 5.3 submitted by the organizations to the the potential for off site consequences from a terronst attack Is possible.

Commission on March 12, 2001 regarding Haddam Neck Reactor's License Termination Plan (Docket No. 50-213-OLA).

'4 "10 of reactor sites, an onsite Sincerely, CL-50/22 13. Given the repeated and serious exposure of workers during decommissioning 1,3 NRC Inspector should be required throughout decommissioning to protect worker health and safety.

through CL-50/23 14. Nuclear corporations should not be allowed to decomnission reactors under an operating license a series of amendments nor should they be allowed to create an Independent Spent Fuel Storage Deb Katz Installation (ISFSI) under an operating reactor license when they are decommissioning Executor Director Decommissioning reactors Installing ISFSIs should be required to go into a part 72 license to provide Citizens Awareness Network adequate regulatory oversight protect public health and safety. The part 72 general license provision for creating an ISFSI at an operating reactor was never Intended to cover a decommissioning reactor Rosemary Bassilakis when regulatory oversight is minimized.

Researcher ISFSL At present, the creation of an ISFSI Citizens Awareness Network CL-50/24 15. Public participation must be Instituted for the creation of the falls into a regulatory no man's land At the NRC pre-hearsng on the Yankee Rowe LTP, the NRC administrative law judges were Instructed by the commission not to address any contentions concerming the storage of high-level radioactive waste. The creation of the ISFSI has serious consequences for each reactor community that could last hundreds of years. That the public can not participate in the process - give comments, request hearings, Intervene -is unreasonable and undemocratic.

now z CL-50/25 16. Given the recent experience with wild fires at the Los Alamos and Hanford Nuclear Reservation and and the potential for flooding and massive soil erosion, the NRC should re-evaluate risk assessments C: dose calculations for decommissioning reactors.

CL-50/26 17. Methodology must be established to determine the extent of underground tad waste contamination and (21 burial. The Multi-Agency Radiological Site Survey and Investigation Manual (MARSSIM)

0) establishes measurement criteria for only 6 inches below the surface of soil. MARSSIM does not co (n

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cii P I 2-01-2002 O0,00AM FROl Dth-Y 31. 725 7676 P. 2 00 1-31-2292 11-59PM FRal CR'"t31A 725 7676 Cn CD University City, MO 63130 radioactivity will have decayed to levels indistiugushable from normal background, well within the Kay Drey 515 West Point Ave safe structural lifetime ofthe entombment structure. The presence of any olobium-94 was ignored.

3CD '.- .1 L-3 Janiamy 30÷ 2003J The amount ofnickel-59 formed inthe relatively brief operating life of thee early plants was W.1 sufficiently small as to presenit no signiuficaid hazard. However, ia large power reactors that have Choie, Rules and Directives Branch operated for 30-40 years, the induced ntobomt-94 and mckel-S9 activities in the reactor vessel and Its internalstructures are well above mnconditional release levels and, since nikkel-59 has an SO.f00 US Nuclear Regulatory Commission A=ns Mkhael Masnik, Ph.D. year half-life and niobmum-94 ha a 000 ver half-hf' the radioactivity will not decay to Washingon, DC 20555-0001 Fax: 301-415-3061 /i unconditional release levels within the foreseeable lifetime of anyman-inade surface structure.

("Technology, Safety and Costs of Decammissioning a Reference Pressunzed Water Reactor Power Stanon." NUREAGCR4-I30; pp. 4-5, 4-6; emplhais added)

Comments on the Draft Supolement to the 1988 "Geneu*i Environmental Impact Statement on DeiomissioninP of Nuclear Facaliiess."

Nickel-59, mentioned above, is produced when the nickel-58 in stainless steel captures electrons.

Since the EPA fourn corrosion products in the sediment of several metals for which they tested, is it not possible that otler metals subjected to the reactor's hostile environment (repeated cycles of CL-51/1 The pnmuayresoolt am a submiting im the following commncts is to urge the Nuclear Regulatory Commission to maintain its commitment to study the operating history and resulting contamination temperature and pressur;e high neutron fluxes, hash chenucals, etc.) may also have degraded or of each reactor on a site-specific. hot generic basas - in its effort to design appropriate CL-5114 dissolved. and migrated out of the plant? Could they be detected in ie sediment if tested? Some of the corrosion products identified in the oxide layer Causd") ofvarious reactors include isotopes of decontamination and decommissioning requirements for each site. Only in this way can there be (1 would be happy to send a copy of the ironi.-, molybdenum, tungsen. titamiu. and carbon.

any hope ofach¢ving the reqiosstce long-term isolation of the contaminants from the human comments I submnited to the NRC on July 16,1980, regarding the Draft Environmental Statement envirosusnens on the proposed use ofcbehe to decontaminate Dresden One in Illinois. Information on chemical denommissioning requir sgti-specfiz and deeonsaamnsation is cited fror AEC, EPRI, GE repos and mo=re.)

1. Site speefietty: Many questions regardin getor CL-512 specific analyses. The Callaway plant, for exarpl, here in Missur, 13locato about 5.5 rolta

2. Rubblization: This word is relatively new to me. But amazingly, the concept is not. I "0 away from the Missouri River, the source of the plant's cooling water and the depository for its remember when our family first drove by the Elk River reactor in Minncsota n a bnef educational liquid efflucnL It would seem that testing would be needed of the unusually long effluent-discharge saide trip with our children. This was some time before November 1974, whes, I first began reading pipe in order to determine where leakage may have occurred during the plant's operation and where and working fulltume against nudele power. When we drove by Elk River again, four or five yewas soil excavation may therefore be reqwured as a pail of the deconm=ioning. later, the plant had completely disappeared.

Sediment samples would be needed where the discharge pipe releases the plmat'S effluent into the Several years after that I learned from one of the former Elk River workers thi they had used Missoun Rivet. Without such site-pecific analyses. a determination of the extlent ofthe nverbed's explosives to "dismantle" the plant. I was incredulous then; I still am. The ist ofexplosives contamination would not be possible. According to a series ofrepoets published in 1970,1974 and employed for the iubblhzation ofthis one small reactor is impressive, or more precasely, worrisome:

1976, by the US Environmental Protection Agency's Office of Radation Protxams, radioactive PETM(pentacythrtol tetranitrate), 115% high velocity gelatin dynamite, cast I'NT (high detonation fission and corrosion products tracuabl to Dresden-One, Haddm Neck, and Oyster Creck had pressure primers), binriay e-negy system (liquid explosives) and water gel explosives. (From the accumuulated in those reactors' dscharge aras in the Kankakee River. the Cotinecticut River and revised "AEC-.k Rivet Reactor Final Program Report," November 1974. p 31). To quote further Bamegat Bay, respectively. (BRWDER 70-1; EPA-520/3-74-007; and EPA-520/5-76-003). from tbat repors=

CL-51/3 Reactor contaminants in the sediments In the EPA studies included cesum-134 and -137, cobalt-S8 For obvious econooue reasons, it was desirable to dispose of as much demolItion debris as possible and--60, manganese-54, and antimony-125. With evidence that these lsotopes were able to bypass in local landfills. Beec" there were no burial facelities for radioactive msaials in the State of the liquid waste filters, it would seem probable that other fission, activation stud corrosion products Minnesota. and because of existing adverse public reacti'on to the nuclear industry from crtam could have, too. And of course some reactor isotopes are extremely long-livetL I am rcminded of sectors, great pains were taken to insure that little, if any, radioaacrtvy remained in the structures that the following discussion in a 1978 NRC publication on decommissionig: were disposodof mMinnesota. For these reasons, the term 'detestable reacdr originated radioactivity' or DROR was specified conracually and defined for this project. It should be Based on the guidance put forth in (Atoek Energy Commission] lRgulatory Guide 1.86 emphasized that DROR as defined below is unique gothe Elk River Reactor project, is a one-tune

[jTenrmuation ofOperasung icenses for Nuclear ReaCtors," June 1974], etiiuvbment of&reactor requirement, and there is no intent to suggest a guideline for future decosummssionang a&tions or to facility requires the e*casement of the radioactive matenals in concrete or ol her structural udaterial supercede guidelines Issued by the [AEC) Director of Regulation. The term DROR was applicable sufficiently strong and strucuratlly long-lived to asture raenttion of the radioactivity until it has only to demolition rubble that was to be left in the State of Minnesota and w.ts defined procedurally decayed to levels which permit unconditional etlesse of the site. (In previous reactor by a special sampling and analytical method. (pp. F-4, -5) decommissioning. it was as*tmed possible to entomb the react" ptesure vessel end it internal structures within the biological shield since the principle source of rediologi.al dose was cobalt-60, which decays with a relatively short hlf-lif (S.27yesas) Thus. within about 100 year* the residual 4yedk&~- 2 z0 CD 3

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(Elk River ltid operated] for thde fu wvw

• retctivo radioactive wastes with roller skates on.) If chelates are used during decommissioning, will the it was dismantled. Thus, the concentratloiS of the longer-lived radionuclides m the Elk River reactor discharge water containing the dissolved, chelated radioactive wastes be kept isolated from the were quite small compared to thie os that will be present in a large PWR [lressorlized "water mactor] after 30 EFIY ofoperetlot. (p.7-16; emphatis added) environment until the chelases are broken down?

tompletely dismanded CL-51/5 I understand that Elk River Is the osly US commercial reactor that lihsbeen You will perhaps be interested in the foIlowing comment by Robert Bernero, who at the time was down to its original greenfleld state. It so completely disappeaed, in fact. that it is sot even the NRC's assistant director of material safety studies. He was quoted in a Juc 19, 1974 Miami mentioned in the "Draft Supplement," in the tables of "permanently shutdown plants" (for Heral article as saying that "the NRC staffcurrently favors a policy that would require example, at pp 3.27,4-44, and Table F-1). And speaking ofAppendx F. by the way: please note decontamlnatios and dismantling after a unit is retired from active service. 'Itdoesn't maie any in Table F.2 that the Callaway plant Is located in Missouri, not in Montana. sense just to seal up a nuclear power plant and leave it,' he ;ays. 'An orderly society should select CL-51/6 jtprp .'

sit_* for Oat burial grounds for its nuclear wilste. It should not exieq to use ower P slant CL-51/7 It is extremely important for the NPC to level with the public about the potentil hazards of the "(emphasis added) concrete debris and related rubble from the dismantled plants. The porous concrete floors get radioactively contaminated during the operation of the plant. "Radioactive corrosion products and CL-51/12 I find it hard to believe that the massive stuctures of concrete and steel reinforcing bars found in a fission products from failed fuel, which are transported throughout the station by the reactor coolant typical commercial power plant could be rubblized. The oomplexity and size of the task seem strean a, are the principal contributors to the more mobile radioactive contamination on piping. overwhelming, What technologies could be used to dismantle the base mat el'the Callaway reactor "U floors, and pool surfaces." (NUREG/CR-0130, June 1978, p.7-15.), Radioactive products can alto building, for example: 13,400 tons of concrete plus 1,470 tons ofintertwined #18 reinforcing steel enter the primary cooling water from pin-hole leaks In the fuel red cladding; from the fissioning of CL-51/13 bars? Do most 1,000-megawatt pressurized water reactorcontainment buildl gs have similar base 01 "tramp uraunium" left on the surfae of the fuel rod during the fabrication of the fuel; and out of CL-51/14 mats? How can the radioactive content of this structure be accurately estimatod? Ifrubblization defective welds at the top and bottom of the fuel rod. The cooling water gets contaminated, and it CL-51/15 were technologically achievable, whereWould on a plant site could the wastes be stored in perpettuty?

can and does leak onto the plant floors during venous routine and accidental activities. Would that be above grade or below? a leachate collection system be requited where the rubble is stored in order to monitor for potential impacts on the groundwater?

Radioactive fission gases that escape out of the fuel rods can also escape out of the reactor vessel.

Some dissolved and entrained noble gases are released to the envirorment in the plnt's liquid CL-51/16 Since the NRC would no longer have regulatory authority over the site, what governmental institution or corporation would be entrusted with the long-tern collection, monitoring and analyses wastes Some are vented or purged into the atmosphere. And some migrate ilto the porous walls, 7 the base mat (floor) or other sub-grade concrete, or the dome or roof of the buildings Radon gas, of the groundwater samples Who would determine If remediation were needed; who would be for example, once m the interstices of the concrete, can decay or break down into radioactive solid CL-51/17 liable for the costs of off-site contamination or other accidents? Who would Ie responsible to daughter products, such as lead-210 that remains radioactive for more than 200 years. Xenon CL-51/18 protect against the inadvertent recycling ofradiioactively contaminated building rubble and soil into Isotopes that permeate the concrete break down Into cesium, including Cs-I 35 with a half-life of 2.3 new construction or as fill, a possibility mentioned but basically discounted in SECY-00-0041, a million yeas. And krypton, also a fission ga., breaks down into rubidium, and then into strontium. letter about rubblized concrete dismantlement, from William Travers, NRC Executive Director for Operations, so the Commnissloners (February 14, 2000)?

As was admitted during the years ofnuclear weapons testing and fallout, cesium and strontium are notoriously radiotoxic. As daughter products of the fission gases, they could rimain entrapped in CL-51/19 3-_-Ml., Because of current efforts to restructure amd deregulate the electric power Industry, the rubblized concrete, releasing radioactive particles and rays into the air for .t least ten half-lives, decisions about decommissioning could be driven by economic consideration% not by safety - by or they could leach into the grourdwater. The rote of dispesal ofthe radioactve and bazardous contaminants in the rubble canmot be accurately predicted. Natural phenomena, for example, could efforts to cut costs in order to stay competitive. I believe the electric utilities ihould not be relieved affect the susceptibility of the radiation to be released. (Regulatory Guide ,S.8,p 2) of liability for their decommissioned reactors z CL-51/8 Because of the potential presence of highly radioactve "hot particles" in unexpected areas CL-51/20 Because ofdetegulitton, the US public must rely more than ever upon the NRC to maintain its C throughout the plant, particularly in the reactor containment building, the rubblized materials authority and responsibility to identify, assess and regulate the 1ul range of potential, hugh-risk m proposed for on-site disposal could be more than just "slightly" contaminatrd. Contrary to the Draft impacts oifevery commercial reactor - before, dunng and following its decommissioning The NRC is our only option.

o Supplement, at page 1-7, for example, I think it is important to note that the rubblization ofconcrete could have radiological impacts as well as non-radiological ones. This is of special significance if 01

0) CL-51/9 explosives are to be used for the demolition, which will generate radioactive figitive dust.

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-D the license is terminanted. At that poin, the NRC no logeer has rcnulatorv authority over the site.

CL-51/21 4. The thrata of terrorism: With terrorsm now a legitimate concern in du United States, the and the owner of the sitt i5 nO iect to NRC regulation$." (p 1-7: emphasis added) b0n potential of a*suicide assault on a nuclear plant - whether the plant is operable or decommissioned

- must be assessed plant by plant, not gneically.

CL-51/25 The federal government (the US Atomic Energy Commisson andits progeny i initiated and fuided the promotion of nuclear power. How, then, can it walk away from the long-verm surveillance of of the nadooi's high-level waste (irradiated reactor No f*.clity exists for the permanent disposalSC, the plant sitcs. even though it will have declared the residual radioactive conLimnmation to be at CL-51/22 fuel), and only one burial site, in BamwelL is currently available to most reactors for the rest of permissible levels? As happened here in St. Louis at the Mallhnckrodt Chemical Works, buildings their wastes (their so-called 'low-kvcl" wastes, which ultimately could include the rubble and and land contaminated in the years 1942-1957 were cleaned up to contaminant levels declared to be dismantled components from decommissioned plants). That one "low-level" waste facility, safe for unrmstcted use by the public. Not many years later, however, some tf those same however, that is serving most ofthe nation, is expected to be closed in th neair future to non buildings and open spaces were found to require majc Iaddittonal remediation because radiation Southeast-US reactors. standards had became more stringent, reflecting &greater understanding ofth- health hazards of radiation. Monitoring eqipmcnt also had become somewhat more sophisticated.

Because of the lack of off-site disposal facilities, it in understandable that the NRC staff would be promoting rubblization, and on-site burial and bunkering of the rubble after deomnm, siorung. many years According to the Code of Federal Re, latio-" Tide 10, 50.32; "Decommissioning will be CL-50126 Concerns and unknowns about the decommissioning of nuclear power plants =tarted ago. In January 1975, for example. Sheldon Meyers, as director ofthe EPA's Office ofFedcral completed within 60 years of permanent oesastionofoperations." That time fame takes i all Activities, included the following observation about the Callaway plant's drat environmental reactors in operation today. Even if off-site disposal space were available to host all the nation's statement: "The sctuon in the draft satement regarding decoiriussioning of the plant indicates the decommissioning rubble, the eros --ounrty transporting of such large vol'unei of waste would plant site may require long term surveillarc after being shut down. This section should be probably be prohibitively expensive and would no doubt be protested by the r.sidents of the expanded to provide an estimate of the length of the surveillance time and the length of time the corridor commutues.

land must stard unproductive. ITshould also identif&w will be resconsible for the surveillance is activitv and whp will ineur the cost" (Pubhshldaby the NRC In March 1975; p. A12, emphasis

"-U CL-51/23 The transformation of the nation's abandoned nudear power plants into de to waste facilities added ) Why has no one answered these concerns prior to now? Or are there no Credible answers?

worrisome from environmental, safety and national security standpoints. To quote from President 0 George W. Bush's Stare of the Union address yesterday. "Our discovenes in Afghanistan 6. Some concludtne comments:

0)J lbarDleusequled by the cofirmed our worst fean.... And the depth oftherv our -emies' madness of the destruction they design. We have found diaarrms of Anmrican nuclear nower P-a~ts and public water facilities ... ." (NYT, Jan. 30. p. A22; emphasis added) CL-51127 I guess one of the reasons I wanted to comment on this "Draft Supplemeat" is because it so dramatically reflects the backward world ofAlice in Wonderland and ofcon nuclear power:

xercial "Sentence first - verdict afterwards." Make a permanent mes first- try to figure it out Articles published for decades have predicted today's disturbing conundrum: The Wall Street afterwards.

Journal on October 12, 1977 - "Scrapping the atom; U.S. is facing problem of how to dismantle used nuclear reactors; Agency hat for not having long-term burial plan; Tomb'i and mothballing; Because I have been suidying and opposing nuclear power for 27 years. it shotdd not surprise you Can a big plant be cut up?" The Mimi Herdad ?onJune 18, 1979 -"Nuclear cleanup: Power That my dream would be for America's nuclear electric utilities to expedite the shutdown of all their plants generate along-term dilemma." The Progressive nDecember 1977 -- "A Landscape of reactors. The questions raised above - and I have many mote - are not meort to be hostile and Nuclear Tombs: What will we do with deactivate reactors and who will pay for doing it?" TIe are certainly not meant to suggest that decommissioning a reactor should be made more lnterdoendens of the United Nations Asan., September 1977- "How do you get rid ofa dead burdensome, dangerous or costly than its continued operation. On the contrary.

nuclear plant?" TecIrnologX Revi of UIT, June/July 1979 - "Deeommussiomng Commercial Nuclear Reactors: Nuclear power plants do not last forever. In the United St*tes some large The longer the reactor operates, the greater will be (1) the levels ofradiation to which the commercial reactors are scheduled for decommissioning within the next 20 years and many others demolition workers will be exposed, (2) the volumes ofradioactve waste generated and stockpiled; will follow. But the process and its costs are still subject to uncertainutes" and (3) the risk of a major radiological emergency. And now I guess we should add, the greater will be the potential for acts of radiological sabotage or terrorism (as per 10 Cl R Part 73).

The more I learn about nuclear power's radioactive waste, the more I wonder if and %ien its proponents will admit that no safe solution may ever be found.

CL-51/28 lhc reactors must be decommissioned in aprudent manner that will seek to protect the health and safety of the workers and the public. In the United States we must rely on the 'guclear Regulatory

5. Concerns - from the past and Into the future:

Commission for its knowledge., guidance and surveillance I hope that trust is Warranted.

CL-51/24 Surely the most surprising and disturbing pronouncement in the "Draft Supplement" appears on Sincerely, page 1-7: "The decommissioning process continues until the licensee rrques. termination of the license and demonstrates that radioactive material has been removed to levels that permit termination of the NRC license. Once the NRC determines that the decommitsioning is completed, 6

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ENVIRONMENTAL COALITION ON NUCLEAR POWER A fundamental obligation ofthe NRC is to protect the health and safety of the public and Judith H. Johnsrud, Ph D, Director "' rr' 21 M; - 2I CL-52/4 the quality of the environment -the general welfare - from radiation-related harm Failure of Headquarters- 433 Orlando Avenue Phone: 814-237-3900 NRC regulatory control to require that the radioactively-contaminated materials and whastes State College, PA 16803 E-mail: iohnsrud~ lkl.nes. ' remaining at a reactor site post-closure will not be released into the biosystem -. as described in this document and in NRC regulations - constitutes a serious violation of the provisions of the Chief, Rules and Directives Branch Atomic Energy Act, as amended, Chapter 1, and of the National Environmental Policy Act. Any Division of Administrative Services RE: Draft Supplement I to the Final Generic such decisions by the NRC are therefore arbitrary and capricious, and contrary to both the AEA Mail Stop T 6 D 59 Environmental Impact Statement on and NEPA.

U S Nuclear Regulatory Commission Decommissioning of Nuclear Facilities, Washington, DC. 20555-0001 NUREO-0586 In practice, in the decommi-sioning of reactors the NRC's Decommissioning Rule has CL-52/5 both allowed release into the environment ofradioactive materials and wastes and disallowed

Dear Madam or Sir:

. members of the affected public from an opportunity for adjudicatory hearings In advagiie of CL-52/6 decommissioning activities. These denials of access to the judicial system are currently being The following comments on Draft Supplement I to NUREG-0586 are submitted on behalfof the Pennsylvania-based Environmental Coalition on Nuclear Power (ECNP) We "extended in the form of NRC's proposed Rule, "Change of Adjudicatory Process," coiipounding CL-52/7 the illegalities inherent in this Supplement. Increasingly, no forum is available to citizens in CL-52/1 concur with and adopt by reference the comments of the Nuclear Information and Res t :e which to exercise their rights under the Federal Administrative Procedure Act This is )et Service, submitted by Paul Gunter anothe reason that this Supplement is unacceptable and should be withdrawn.

In our state, decommissioning of the Shippingport reactor, Saxton and Waltz Mills CL-52/8 Furthermore, a "generic" EIS cannot provide adequate assurance that the unique situation experimental reactors, and the Quehanna industrial nuclear facility and former reactor ha%a '5 and condition of each nuclear facility have been fully analyzed and accounted for Each plant is occurred. The old Molycorp thorium processing facility near Washington PA is currently in the unique; each plant's impacts must be examined in relationship with all other nuclear facilities

'a early stages ofdecommissioning. The Peach Bottom Unit I and Three Mile Island Unit 2 that affect the condition of the environment In the real world environment, radioactive and "4 reactors have been awaiting decommissioning for more than twenty years. The nine ether hazardous materials are not necessarily static, they move; they interact with other materials; they operating commercial reactors will ultimately also require decommissioning upon expiration of accumulate; they may have their adverse Impacts at or near their site of origin or far away from it. -s their operating licenses, as will numerous other industrial and research nuclear facilitiMs The totality of those impacts, upon both human and non-human inhabitants of the biosphere, must be incorporated into an environmental analysis and accounted for fully also for adversely CL-52/2 .This Supplement to the Final GEIS fails to address decommissioning of nuclear facilities affected individuals in any cost-benefit analysis. All issues should be examined at each plant.

other than commercial reactors. It therefore fails to take into account the subject of NUREG 0586: the environmental impacts of decommissioning nuclear facilities - all nuclear facilities CL-52/9 Exclusion of licensee decisions and actions prior to certification that plant operaions CL-52/3 Moreover, in order to assess the full environmental impacts ofeach facility's decommissioning, have permanently ceased means that the Supplement fails to consider factors that may have it is necessary to take into account its impacts in concert with the impacts of all other luclear negative impacts on the quality of the decommissioning activities and on minimization of the facilities that contribute additive radiological and other contamination to the biologic system. quantity and condition of the wastes resultant from the handling and removal of radioactive CL-52/10 materials from plant structures, systems, and components. Exclusion from consideration of the Pennsylvania remains the Host State for "disposal" of the "low-level" radioactive wastes fate of contaminants post-license termination also renders this Supplement insufficient and not generated in the Appalachian States Regional Compact, despite failure of the contractor. Ch.m Nuclear Systems, to site a LLRW disposal facility. The Department of Environmental Protection CL-52/11 acceptable to account for the environmental impacts of decommissioning. In effect, the NRC plans to wash its hands of any responsibility for the long term damage that may result from recently adopted expanded permissible disposal of radioactive materials at municipal landfills reactor decommissioning (and that ofall other nuclear licensees' facilities and activities. It is Pennsylvania has not yet obtained Agreement State status. Our law provides for regulation by the state or municipality and community in which a plant is located and the residents that will be the state of radioactive materials and wastes ifNRC releases them from its regulatory conrcl. required to bear the burdens of injury and costs of further clean-up after the NRC has vanished Z Moreover, the Pennsylvania Constitution provides that the people of the Commonwealth Underlying these failures of the agency's responsibility for the facilities and activities that r have the right to a clean, livable environment foe themselves and for their descendants. Thus, for CL-52/12 Ithad sanctioned by granting an operating license and through its regulatory actions and inactions these several reasons, the decommissioning decisions of the NRC are of substantial concern to is the failure of the NRC - and of EPA - to set radiation protection standards that recognize the ITI residents of this Commonwealth, where the nation's worst commercial nuclear power accident G) has not been forgotten.

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CD t3 CL-521 3 great varieties of adverse effects of low-level radiation on human beings. Affected populations

_are composed of many individuals who are not close to being that "standard man" in whom the site decontamunation is CL-52/14 NRC places so much faith. The trans-solutional problem of complete here evident: the NRC does not require the return ofa decomnissioned facility and site to its pre of wastes is high, and CL-52/15 operationaJ radiation level. Because the costs ofsequestrauon ("disposal')

deemed to be a "burden" for the licensee, the agency continues its endeavor to allow massive deregulation - release, recycle, and re-use - of radioactively-contaminated materials and wastes and their entry into the "free market" for resale and reuse in a host of consumer products or CL-52116 Subsequent uses of these "slightly contaminated" materials and wastes - in roadbedb, construction, consumer products, or other objects inwividuals may contact - will each add to the exposures from CL-52/17 radiation doses received without knowledge or consent of the recipient. These multiple unmonitored. unlabeled, uncontrolled sources are in no way accounted for, but they are additive and cumulative for that individual. They violate the fundamental tenet ofradlauoa protection. va, that the recipient of a radiation dose that is in addition to naturally-occurring background exposures should receive a benefit equal to or greater than the risk incurred. The CL-52/18 NRC should not permit radioactive materials or wastes to be released into the environment. That is the basic message, the rightful demand of all those who will be affected negatively by releases.

es, it is CL-52/19 As techniques of'research and analysis in complex biological systems rmpro-becoming more apparent to thoughtful, careful scientists and regulators that it is impemtive to Co include the impacts of low-level radiation exposures on all forms ofliving beings, not merely on CL-52/20 humans But it is also increasingly important to incorporate into radiation protection standards CL-52/21 low-dose effects. An EIS must also consider the effects of the synergies between and among ionizing radiation and the multitude of hazardous materials also released into the environment.

CL-52/22 - Instead, the NRC has chosen to abandon its former regulatory philosophy (defense in depth and redundancy of safeguards) in favor of the far less restrictive and less protective CL-52123 approach (performance-bascd and risk-informed). The relaxation of regulatory control is also evident throughout this draft volume. Decommissioning is the fimal chapter for the agency in its relationship to a givea site and license. For people, the community, municipality, and state, it is the beginning of an essentially endless association with a nuclear site that may continue to CL-52/24 endanger their lives and environment. The NRC has a statutory obligation to do a betterjob CL-52/25 These admonutions have been presented to the NRC repeatedly in many Commission and staffmeetings, agency pangls and workshops, public hearings, legal proceedings. Until they are heard, adopted, and adhered to, this Supplement, the Final GELS on Decommissioning of Nuclear Facilities and the Decommissioning Rule and NRC's radiation protection standards will contiuue to be inadequate and in violation of the applicable laws, including but not limnted to the AEA, NEPA, and APA cited above. All four should be withdrawn and entirely rewritten to provide true protection from radiological contaminations.

Sincerely, z

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I - San Luis Obispo Mothers for Peace

/ g 'Z/Al plant but dealing also with storage and transportation oftlethal substances unforeseen when licenses were panted.

PO 164 Pismo Beach, Ca 93448 Observations:

(805) 773-3881 beckers@thegrid.net SLOMFP reviewed the four transcripts from the four meetings held by the NRC on the draft GEIS and was appalled by the waste of taxpayer dollars.

Comments of the San Luis Obispo Mothers for Peace CL-53/5 The NRC gave 10 Individuals representing 10 different environmental groups only 5minutes each to express their concerns. Furthermore, it is outrageous that On the NRC Draft GEIS on Decommissioning the NRC located these proceedings hundreds ofmiles firom the affected communities Nuclear Power Plants and those who are most concerned about the decommissioning of nuclear plants. There is no doubt that the lack of public participation was due to the location of the meetings, The San Luis Obispo Mothers for Peace (SLOMFP) is aware that the comment not to lack ofpublic concern. Mr. Cameron has heard this concern expressed In the past.

period ended on January 30,2002. Regardless, it is compelled to submit the following comments on the draft GEIS and observations from transcripts of NRC meetings. CL-53/6 Both the NRC and taxpayers would have been better served by sending the draft GElS to all individuals and groups that have demonstrated interest in safety Issues at nuclear plants over the last two decades, with a questionnaire, a comment section, and a self Comments: addressed, stamped envelope.

1. The SLOMFP echos the statement ofSara Barczak represen ing Georgians Sincerely, for Clean Energy at the Georgia meeting regarding the following:

Rochelle Becker February 2, 2002 CL-53/1 a. SLOMFP is troubled by the Inability of the public to have adequate access to the NRC website. PNior to the censorship, the existence of the website had San Luis Obispo Mothers for Peace 0

?k3 been viewed as a giant step forward in communication between the public and the Cc: Senator Dianne Feinstein Commission.

Senator Barbara Boxer CL-5312 b. A reduced security force at a decommissioned nuclear plant increases the threat of terrorism. A thorough amended review of necessary security measures during decommissionIng of nuclear facMlities [due to 9/Il] must be compiled by the NRC and added to the supplement.

CL.53/3 c. Existing nuclear power plants are not generically designed and.

therefore, ageneric prgrm for decommissioning is completely inadequate to protect public health and safety. New and site specific Environmental Impact Statements must be required to address how different power plants should be decommissioned (from the standpoint of historical operations. age-related degradation, salt water lntrusionhED in the safest manner possible for each location. In the case of Diablo Canyon, new seismic information should be sought to assure the public that the process would not increase the dangers of an already dangerously sited nuclear plant.

z CL-53/4 d. When California's nuclear plants received licenses for construction and operation, promises were made that high-level radioactive waste would be removed within a few years. Every deadline to open a safe and permanent repository for high-level radioactive waste has been missed. Therefore, the G) issue has grown; we are not accessing only the decommissioning of a power 6

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NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION 1 REPORT NUMBER (2-89) (Assigned by NRC, Add Vol. Supp, Rev, NRCM 1102. BIBLIOGRAPHIC DATA SHEET andAddendum Numbers. Ifany.)

3201.3202 (See instructions on tMe reverse) NUREG-0586, Supplement 1

2. TITLE AND SUBTITLE Volume 2 Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities DATE REPORT PUBLISHED 3

Supplement 1 YEAR Supplement Regarding the Decommissioning of Nuclear Power Reactors MONTH Final Report November 2002

4. FIN OR GRANT NUMBER 5 AUTHOR(S) 6. TYPE OF REPORT Technical 7 PERIOD COVERED (Inclusive Dates) 8 PERFORMING ORGANIZATION - NAME AND ADDRESS (IfNRC, provide Division, Office or Region, US NuclearRegulatoryCommission, and mailing address,dcontractor, provide name and mailing address)

Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 9 SPONSORING ORGANIZATION -NAME AND ADDRESS (f NRC. type 'Same as above',d contractor,provideNRC Division. Office or Region, US NuclearRegulatory Commission, and mailingaddress )

Same as 8 above

10. SUPPLEMENTARY NOTES

11. ABSTRACT (200 words or less)

This document is a final supplement to the NRC Generic Environmental Impact Sta tement on Decommissioning of Nuclear Facilities (GElS), issued in 1988 as NUREG-0586. This supplement was prepared because of the technological advances in decommissioning operations, experience gained by licensees, and changes made to NRC regulations since the 1988 GELS. It is intended to be used to evaluate environmental impacts during the decommissio ning of nuclear power reactors as residual radioactivity at the site is reduced to levels that allow for termination of th e NRC license. This supplement addresses only the decommissioning of nuclear power reactors licensed by the NRC. It updates the sections of the 1988 GElS relating to pressurized water reactors, boiling water reactors, and multiple reactor statio ns. It goes beyond the 1988 GElS to consider high-temperature gas-cooled reactors and the fast breeder reactors. This docum ent can be considered a stand-alone document and the environmental impacts described herein supercede those describ ed in the 1988 GElS.

The scope of this supplement is based on the decommissioning activities perform ed to remove radioactive materials from structures, systems, and components from the time that the licensee certifies t hat they have permanently ceased power operations until the license is terminated. An evaluation process was develope d to determine environmental impacts from the specific activities that occur during reactor decommissioning, based on data fr om site visits and from licensees at reactor facilities being decommissioned. The data obtained from the sites were analyze d and then evaluated against a list of variables that defined the parameters for facilities that are currently operating but whi ch one day will be decommissioned. This evaluation resulted in a range of impacts for each environmental issue that may be used for comparison by licensees that are or will be decommissioning their facilities. The staff has considered public c omments received during scoping and on the draft in preparation of this final supplement.

13 AVAILABILITY STATEMENT 12 KEY WORDS/DESCRIPTORS (List words orphrases that will assist researchersin locatingthe report) unlimited Supplement to the Generic Environmental Impact Statement 14 SECURITY CLASSIFICATION Decommissioning (This Page)

SAFSTOR DECON unclassified ENTOMB (This Report)

Rubblhzatbon unclassified Site release 15 NUMBER OF PAGES Ucense termination Environmental impacts Post-shutdown decommissioning activities report 16 PRICE NRC FORM 33S (2-89) "Thisform was elecironically produced by Ehte Federal Forms, Inc

• pPrinted

("plaper Federal Recycling Program

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300

August 12, 2016 Via U.S. Mail and Email Cynthia Herzog Marlayna Vaaler, Project Manager /

Senior Environmental Scientist U.S. Nuclear Regulatory Commission California State Lands Commission Office of Nuclear Material Safety and Safeguards 100 Howe Avenue, Suite 100-South Washington, DC 20555-0001 Sacramento, CA 95825 Email: Marlayna.Vaaler@nrc.gov.

Email: CEQAcomments@slc.ca.gov

Subject:

Environmental Review Scoping Comments for the San Onofre Nuclear Generating Station Units 2 & 3 Post-Shutdown Decommissioning Project

Dear Ms. Herzog:

On behalf of the City of Laguna Beach ("City"), this letter provides preliminary scoping comments on the Notice of Preparation (NOP") of a draft environmental impact report ("DEIR") for the San Onofre Nuclear Generating Station Units 2 & 3 Post-Shutdown Decommissioning Project

("Project).

A portion of the proposed Project is located within the jurisdiction of the California State Lands Commission ("SLC"), on land within the Marine Corps Base Camp Pendleton, three (3) miles south of the community of San Clemente, west of Interstate 5 (I-5) and adjacent to the Pacific Ocean in northern San Diego County. The Project consists of the following four phases:

• Phase 1 -Decontamination and Dismantlement (2017-2025);

• Phase 2 - Partial Site Restoration and Offshore Conduit Disposition (2020-2035);

• Phase 3 -ISFSI Operation and Maintenance (2035-2049); and

• Phase 4-Phase 4: ISFSI Removal and Final Site Restoration (2049-2051).

According to the NOP, the Project has the potential to cause a number of significant short-term, long-term and cumulative environmental impacts. The SLC, as the lead agency under the California Environmental Quality Act ("CEQA"), 1 has correctly determined that an EIR is required.

As a responsible agency under CEQA and a cooperating agency under the Nationru Environmental Policy Act ("NEP A"),2 the City respectfully submits the following scoping comments.

1

_ Pub. Res. Code§§ 21000 et seq.; see also Cal. Code Regs., tit. 14, ch. 3, § 15000 et seq. ("CEQA Guidelines").

2 42 USC§§ 4341 et seq.; see also Council on Environmental Quality ("CEQ") NEPA Regulations, contained in 40 C.F.R Parts 1500-1508.

505 FOREST AVE. LAGUNA BEACH, CA 92651 TEL (949) 497-3311 FAX (949) 497-0771

© RECYCLED PAPER

I

~'

Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 2

1. Consultation with the City concerning this Project's traffic, recreation, and open space impacts is required.

On July 12, 2016, the City of Laguna Beach became aware of the Project when City staff received the NOP. Section 15083 of the CEQA Guidelines encourages lead agencies to consult with other interested parties early in the environmental review process. The NOP solicits input from such interested parties, including the City. The City hereby submits these comments within the period requested in the NOP.

Because the Project is one of regional and areawide significance, a scoping meeting is required pursuant to Public Resources Code, section 21083 .9(a)(2). Further, because the City exercises authority over resources that may be affected by the Project, including transportation facilities within its jurisdiction that could be affected, the SLC is required to consult with the City concerning potential effects to those resources. 3 We hereby request consultation concerning the Project's impacts to all potentially impacted transportation facilities within the City and to the area's beaches, adjacent ocean resources, open space and wildlife habitat resources.

• Pursuant to Public Resources Code, section 21092.2, we also request notice of all stages of environmental review for the Project and any and all actions that the SLC proposes to take on this Project. Please send any and all notices via email to the following persons:

a) Mike Phillips, Environmental Specialist, at mphillips@lagunabeachcity.net; b) Christa Johnson, Assistant City Manager, cjohnson@lagunabeachcity.net; and c) Jason Holder, outside legal _counsel retained for this matter, jason@holderecolaw.com.

Additionally, please send paper copies of notice documents solely to the undersigned.

2. Because the Nuclear Regulatory Commission Must Ultimately Approve the Decommissioning Project, There is a Federal Nexus Triggering the Need for a Joint EIR/EIS.

The Project is subject to oversight and review by the U.S. Nuclear Regulatory Commission ("NRC) under Title 10 of the Code of Federal Regulation, Part 50, Section 50.59 (10 CFR 50.59), applying to design changes, tests and experiments carried out at licensed nuclear facilities. The Project involves design changes to SONGS that will ultimately require NRC approval. For example, the NRC will have to approve SCE's license termination plan.

Arguably, the Project also requires a license amendment. 4 When it fulfills its statutory duties, 3

PRC,§ 21092.4; CEQA Guidelines,§ 15086(a).

4 For example, the NRC has not approved the design of the Holtec UMAX system that SCE has proposed for the ISFSI, and that partially subterranean design may reduce radiation safety. The proposed changes and alterations to the SONGS facility's design associated with decommissioning, including the Spent Fuel Pool Island Project ("SFPI") and the expanded and modified Independent Spent Fuel Storage Installation ("ISFSI"), require a license amendment because these changes were never addressed in the SONGS Final Safety Analysis Report ("FSAR") or any of the updates to the FSAR. See 10 C.F.R. §§ 50.56, 50.59(c). In addition, the Updated FSAR also does not consider the effects of sea level rise caused by

Cyrithia Herzog, Senior Environmental Scientist August 12, 2016 .

California State Lands Cominission 3 NRC will be the federal lead agency for review of the Project pursuant to NEPA. To adequately address the environmental impacts of the whole of the Project, SLC and NRC should jointly prepare an EIR/EIS for the Project. (See CEQA Guidelines,§§ 15006G), 15170, 15220, 15222.)

The CEQA Guidelines are clear:

If a Lead Agency finds that an [Environmental Impact Statement ("EIS")] or Finding of No Significant Impact for a project would not be prepared by the federal agency by the time when the Lead Agency will need to consider an EIR or Negative Declaration, the Lead Agency should try to prepare a combined EIR-EIS or Negative Declaration-Finding of No Significant Impact. To avoid the need for the federal agency to prepare a separate document for the same project, the Lead Agency must involve the federal agency in the preparation of the joint document.

This involvement is necessary because federal law generally prohibits a federal agency from using an EIR prepared by a state agency unless the federal agency was involved in the preparation of the document. 5 Similarly, the CEQA regulations for implementing NEPA encourage cooperation with stat~ and local agencies in an effort to reduce duplication in the NEPA pro~ess. 6 In the required Draft EIR/Environmental Impact Statement ("DEIR/S"), NRC should - 'l

<I:"

c fully address the radiological safety concerns that are purportedly preempted by federal law. 7 .,._ .!-

This is the elephant in the room that can no longer be concealed or brushed aside under a blanket claim of federal preemption. The public's interests and legal rights to understand the full

- environmental impacts of the decommissioning process will be circumvented ifradiological . . i.,. **

• -* ~tH'l.

1 safety issues are not addressed in the DEIR/S analysis. .1* . r*

When conducting this analysis, NRC will have to analyze site-specific radiologicatsafety concems. 8 The NRC's past "generic" EIS documents do not satisfy the requirem,ent for deta.iled impact analy~is. These boilerplate analyses do not address the specific circumstances that make SONGS decommissioning particularly worrisome to neighboring stakeholders, including the City'.s residents, businesses, and visitors. In Natural Resources Defense Council v. Morton, the climate change and associated reductions ofradiation safety at SONGS. See SONGS FSAR, Hydrologic Engineering Chapter, available at: http://www.nrc.gov/docs/MLJ 114/MLJ 1145A032.pdf. ,

5 CEQA Guidelines, § 15222; see also id at§§ 15226, 15228.

6 40 CFR § 1506.2.

7 As discussed further below, when recently approving the.ISFSI, the California Coastal Commission did not analyze the "radiological safety" impacts of spent fuel storage casks based on a claim of federal preemption. (See Addendum to CCC Staff Report, dated Oct. 5, 2015 (CCC ISFSI Addendum), pp. 10-11, available at:

http://documents.coastal.ca.!:!ov/reports/2015/J O/Tu J4a- l 0-2015.pdf.) Comments made to the Coastal Commission and inch,1ded in the CCC ISFSI Addendum are hereby incorporated herein by reference.

8

• The 2002 Supplement to NRC's Final Generic Environmental Impact Statement on Decommissioning ofNuclear Facilities (NUREG-0586 Supplement 1) (the "Supplement") does not address storing spent fuel in a seismically active marine environment such as that characterizing the Project site. See generally Supplement, available at:

http://www.nrc.gov/docs/M L0234/M L0234 703 04.pdf.

Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 4 Bureau of Land Management attempted to grant individual licenses, relying solely on a program EIS for the entire licensing program. 9 The court found that the program EIS failed to provide the decisionmaker With information regarding the specific and particular consequences of the action. Io A similar finding was made by the court in Natural Resources Defense Council v. Administrator: "As a general rule, the preparation of a [program EIS] does not obviate the necessity of preparing a particularized impact statement for individual major federal actions that are components of a subject program."I I Several courts have confirmed that site-specific environmental analyses are required before a lead agency can dispense with environmental review. I2 Here,. the NRC' s Supplement generically analyzing the impacts of decommissioning identified two categories of impacts to be site-specific: threatened and endangered species and environmental justice. These issues must be addressed in the DEIR/S for this Project. It also identified four categories of impacts that it termed "conditionally site-specific":

• Land use involving offsite areas to support decommissioning activities

• Aquatic ecology for activities beyond the operational area

• • Terrestrial ecology for activities beyond the operational area .

• Cultural and historic resources for activities beyond the operational area with .P,.o current cultural and historic resource survey. 13

• The Supplement also concluded that environmental justice impacts must be determined on a site-specific basis. 14 The DEIR/S required for this Project must also address each of these site-specific impact categories and any others implicated by the proposed actions.

The NRC's Supplement also acknowledged site-specific analysis would be required when

• circumstances for decommissioning are unusual. Additionally, the NRC's more<recent Generic EIS for Continued Storage ofSpent Nuclear Fuel acknowledged that prior studies did 110(;,

consider seismic risks at western nuclear reactors including San Onofre. Is Here, because,tl;ie Project site is located in a seismically active area and is immediately adjacent to .a sensitive 9

Natural Resources Defense Council v. Morton (1974) 388 F.Supp. 829.

10 Id at 838.

11 Natural Resources Defense Council v. Administrator (1978) 451 F.Supp. 1245, 1258.

12 The Ninth Circuit of the U.S. Court of Appeals, which includes California, adopted similar reasoning. (See, Natural Resources Defense Council v. Hodel (9th Cir. 1987) 819 F.2d 927, 928 (refers toNRDCv. Morton, supra, as the leading case in this area"); City ofTenakee Spr~ngs v. Block (9th Cir. 1985) 778 F.2d 1402, 1407 ("[w]here there are large-scale plans for regional development, NEPA requires both a programmatic. and a site-specific EIS"); Oregon Environmental Council v. Kunzman (9th Cir. 1983) 714 F.2d 901 (Oregon Department of Agriculture ordered to prepare site-specific EIS for herbicide spraying program and had erred in relying on earlier program EIS).

13 Supplement, p. xvi.

14 Id at p. 4~65.

15 See NRC Generic EIS for Continued Storage ofSpent Nuclear Fuel (NUREG-2157), pp. xlii, F-10 :fu. 5, available at:

http://www.nrc.gov/docs/ML1419/ML14196Al05.pd£

• -'I Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 5 marine ecosystem, the site-specific analysis must consider the associated risks of radiological contamination.

In September 2014, SCE submitted a post-shutdown decommissioning activities report

("PSDAR"), the licensee's required analysis of the extent to which the Project's impacts are covered by the analysis in NRC's Supplement. 16 In its PSDAR, SCE asserted that "[b ]ased on current plans, no decommissioning activities unique to the site have been identified and no activities or environmental impacts outside the bounds considered in the GEIS have been identified." 17 The City strenuously disagrees with this conclusion and requests that the NRC conduct an independent assessment of the extent to which the environmental impacts of the Project require site-specific analysis in the DEIR/S, especially given the Project's unique environmental setting.

When engaging in further consultation with the City and other concerned stakeholders, please confirm that the SLC and NRC will prepare a joint DEIR/S that will address radiological safety issues and will support the analysis with substantial evidence.

3. The DEIR/S Must Analyze the Impacts of the Whole Project. *, .

• Both CEQA and NEPA require lead agencies to analyze the impacts of the "whole of the project." 18 Here, the whole of the project is the entire decommissioning process. The NRC defines "decommission" in 10 CFR 50.2 as a process "to remove a facility or site safely from service and reduce residual radioactivity to a level that permits (1) Release of the property for unrestricted use and termination of the license; or (2) Release of the property under restricted conditions and termination of the license." This process necessarily includes each step following the decision to cease operations to the termination of the NRC license.

• Indeed, in* its PSDAR, SCE admits that the decommissioning process necessarily includes Spent Nuclear Fuel. _..

Management Periods. 19 Unfortunately, there has already been a pattern of piecemealed review and approval of various smaller "projects" that are in actuality inextricably connected to SONGS decommissioning. For example, the CPUC approved SCE's decommissioning cost estimate in December 2014. This decision was not preceded by any environmental impact analysis. Then, 16 See SCE's PSDAR for SONGS, available at: http://www.nrc.gov/docs/ML1426/ML14269A033.pdf.

17 See id at p. 8. The PSDAR is ostensibly supported by SCE's Environmental Impact Evaluation ("EIE"). See PSDAR for SONGS, p. 18. Like the PSDAR, the EIE concluded that "SCE's review confirmed that the anticipated or potential impacts are within the bounds of the generic impacts that the NRC described in the decommissioning GEIS." See EIE, p.

ES-3, available at: https://www.songscommunity.com/docs/eieaug 1.pdf. The EIE, however, provides only a cursory review of potential environmental impacts from the Project applicant's undeniable self-interested perspective, and that review relies on multiple unsupported assumptions. An independent review of Project impacts, conducted by state and federal agencies, is required.

• 18 See CEQA Guidelines§ 15378(a) [a "project" means the whole of an action that may cause either a direct or reasonably foreseeable indirect physical change in the environment]; see also McQueen v. Board of Directors of the Midpeninsula Regional Open Space District (1988) 202 Cal.App.3d 1136, 1143; see also Thomas v. Peterson, 753 F.2d 754 (9th Cit. 1985);

see also Save Yaak Comm. v. Block, 840 F.2d 714 (9th Cir. 1988).

19 See SCE's PSDAR for SONGS, p. 8.

Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 6 in 2015, the Coastal Commission approved the SFPI and several months later approved the ISFSI for SONGS. These components of the overall decommissioning project should have been analyzed together in a single EIRJS. Instead, their individual effects have been minimized by chopping up the larger project into smaller pieces.

• The DEIR/S must analyze the impacts of all phases of decommissioning, including the SFPI and the ISFSI. Again, the public's interests and legal rights to understand the full environmental impacts of the SONGS decommissioning process will be thwarted ifthe DEIR/S analysis does not consider all necessary aspects of decommissioning.

4. The SLC Has Broad Authority to Analyze Radiological Safety Issues and to Regulate Non-Radioactive Health and Safety Issues.

As noted above, the City recognizes that some of the issues identified above maybe considered radiologic safety issues that could be preempted under federal law. The Coastal Commission did not analyze many safety issues raised by commenters based on a claim of federal preemption. Specifically, it asserted:

Without assessing the validity of these concerns, the Commission staff notes that;.

the consequences of any failure, malfunction, or defects in the proposed cooling system are related to radiological safety, which is under the exclusive jurisdiction *~ .. ~

of the federal [NRC]. 20 While a state agency may be prevented from imposing restrictions on nuclear. power plants based on federal preemption, nothing prevents the state agency from analyzing radiological safety issues and recommending restrictions (i.e., mitigation measures and .

alternatives) that the NRC can and should adopt.

Further, while both federal and state regulatory agencies have oversight over nuclear power facilities, it is well-settled that state regulators maintain their traditional authority to regulate non-radioactive health and safety issues, including land-use, environmental, and ec.onomic concerns associated with nuclear power generation. 21 SLC regulatory action for this Project is not preempted when motivated by non-preempted concerns and when it neither conflicts with nor frustrates the Congressional purpose of the Atomic Energy Act ("AEA"). 22 Thus, even ifthe NRC does not presently assume its proper role as co-lead agency for this*

Project, for purposes of performing the analysis of radiological safety impacts, SCE must satisfy its duty to analyze non-radioactive health and safety issues.

2

° CCC ISFSI Addendum, pp. 10-11.

21 Pacific Gas & Electric Co. v. State Energy Res. Conservation.& Dev. Comm 'n, 461 U.S. 190, 205, 212 (1983)

(PG&E).

22 Id at 220-223.

Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 7

5. The DEIR/S must adequately analyze the Project's potentially significant impacts to marine life, air and water quality, City transportation and recreation facilities, and it must consider secondary impacts and analyze a reasonable range of Project alternatives.

The DEIR/S must include thorough analysis of the following potentially significant environmental impacts that could affect the City and its residents:

a) Demolition impacts - Impacts to air and ocean water quality during demolition of Units 2 & 3 reactor structures b) Damage to roadways and other infrastructure caused by the transportation of structures, systems, and components ("SSCs"), hazardous materials, and any contaminated soils and water23 c) Impacts to groundwater supplies caused by potential radiation contamination and

• contamination that may have already occurred d) Impacts associated with disposing of spent fuel pool water - Discussion of how contaminated water from the spent fuel cooling pool is disposed of after rods are removed e) Impacts to special status species The NOP acknowledges that four special-status reptiles have the potential to occur within the offshore Project area and that several other special-status species have the potential to occur within the onshore Project site. 24 f) Impacts to marine life if cooling system intake and discharge conduits, and the: fish return system conduit are left partially or completely in place '::.

g) Seismic-related hazards associated with the storage of spent nuclear fuel storage casks for at least 20 years and quite possibly longer2 5

• h) Impacts that may occur if the dry storage casks in the ISFSI crack and release radiological contamination 23 SCE's EIE states that decommissioning will involve the transportation of millions of cubic feet of radioactive and nonradioactive waste. See EIE, p. ES-16. It then explains that "SCE plans to ship the bulk of radiological waste by rail; however, there may be times when truck shipments will be required." Ibid .

24 See NOP, Attachment, p. 19.

25 In a June 2015 staff report, Coastal Commission staff noted that "Though SCE seeks temporary development authorization until 2051, there is no assurance that SCE will be able to transfer the spent fuel to DOE custody and decommission the proposed facility as planned by 2051, complicating the analysis of the project's exposure to geologic hazards and its potential to adversely affect coastal resources. The uncertain duration of the ISFSI's presence at the proposed location also has implications for SCE's alternatives analysis .... " (CCC ISFSI Addendum, Staff Report, p. 20.)

Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 8 i) Cumulative impacts - Please address the potential impacts to the surrounding environment (earth, land, sea, air) of short-term, long-term, and indefinite storage of spent nuclear fuel on the Project site.

j) Mitigation Measures - please include measures to reduce or eliminate all potentially significant Project impacts If the SLC concludes that mitigation measures are within the responsibility and jurisdiction of another agency, such as the NRC, then it must recommend that those measures "can and should" be adopted by that agency.

k) Weekday and peak traffic impacts on all surrounding roads and intersections caused by transporting SSCs, spent nuclear fuel storage casks, and any contaminated soils and water

1) Weekend and off-peak traffic impacts on Highway 1 and SR 133 (Laguna Canyon Road) m) Impacts on the City's recreation facilities including its beaches and shoreline caused by the Project26 n) *Public service impacts to the City's residents, including any reduced police, fire, or ambulance services or increased respo~se times caused by Project activities27 o) Secondary impacts caused by increased Project traffic, including air quality impacts and increased greenhouse gas (GHG) emissions p) Consideration of a reasonable range of Project alternatives, including options for removal of the dry storage casks from the Project site and to either a Consolid~ted Interim Storage ("CIS") location or to a permanent spent nuclear fuel *storage facility Please include all technical support for the above analyses in appendices to the DEIR/S.

We request that the SLC and NRC provide a joint environmental impact analysis that considers the Project in its entirety. The requested DEIR/S must enable fulfillment of duties to protect communities and natural resources by considering and minimizing all potentially 26 The NOP indicates that SLC staff has concluded that the Project would not have any potentially significant impacts to recreation. (NOP, p. 18.) This conclusion is incorrect and is unsupported by substantial evidence. Because the Project is located adjacent to the Pacific Ocean and near several state beaches, it has the potential to impact these recreation facilities.

Those impacts must be analyzed in the DEIR/S and mitigated to the extent feasible.

27 Again, the NOP indicates that SLC staff has concluded that the Project would not have any potentially significant impacts to public services. (NOP, p. 18.) This conclusion is similarly incorrect and is also unsupported by substantial evidence.

Cynthia Herzog, Senior Environmental Scientist August 12, 2016 California State Lands Commission 9 significant impacts of the Project, including those that have heretofore been disregarded as the exclusive province of the federal government.

If you have any questions concerning these comments, please contact Michael Phillips at (949) 497-0390 and at mphillips@lagunabeachcity.net.

Sincerely,

.--1.n~

>al~

City Manager cc: (via email only)

City Council Christa Johnson, Assistant City Manager David Shissler, Director of Water Quality ,,

Mike Phillips, Environmental Specialist Jason Holder, outside legal counsel

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 5, 2018 Ms. Cynthia Herzog Senior Environmental Scientist California State Lands Commission 100 Howe Avenue, Suite 100-South Sacramento, CA 95825

SUBJECT:

ADDITIONAL INFORMATION REGARDING THE CALIFORNIA STATE LANDS COMMISSION RESPONSE TO THE CITY OF LAGUNA BEACH ENVIRONMENTAL REVIEW PUBLIC SCOPING COMMENTS FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3, DECOMMISSIONING PROJECT

Dear Ms. Herzog:

Thank you for the opportunity to review the Draft Environmental Impact Report (EIR) prepared by the California State Lands Commission (CSLC) in regard to the San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS), Decommissioning Project, which was released on June 27, 2018. The operator of SONGS, Southern California Edison (SCE), holds facility operating licenses from the U.S. Nuclear Regulatory Commission (NRC). As noted in your correspondence, the CSLC, as the lead agency under the California Environmental Quality Act (CEQA), has determined that an EIR is required for the SONGS decommissioning project, and is currently soliciting feedback on the Draft EIR. While I understand that the public comment period on the Draft EIR closed on August 28, 2018, I hope that this additional information from the NRC staff will be useful to the CSLC as you move forward with the CEQA process.

In Appendix C of the Draft EIR, the CSLC has dispositioned public scoping comments received as a result of the Notice of Preparation issued on June 12, 2016, regarding the scope and content of the EIR for the SONGS decommissioning project. One of the comment letters, dated August 12, 2016, was received from the City of Laguna Beach, California (the City) and addressed to both the CSLC and the NRC. This letter included numerous comments on the ongoing decommissioning activities at SONGS, and made several requests of the CSLC and the NRC with respect to environmental oversight during this process.

In order to facilitate your ongoing review and finalization of the Draft EIR for the SONGS decommissioning project, in the attachment to this letter, the NRC staff has provided some additional information in support of your disposition of the Citys comments. The Citys letter, as well as other publicly available documents referenced in the attachment, can be found in the NRCs document repository at Agencywide Documents Access and Management System (ADAMS). You may obtain publicly available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ADAMS Public Documents and then select Begin Web-based ADAMS Search.

C. Herzog If you have any additional questions or clarifications regarding the information provided in the attachment to this letter, please contact the SONGS decommissioning project manager, Marlayna Vaaler, at 301-415-3178, or via email at marlayna.vaaler@nrc.gov.

Sincerely,

/RA/

Bruce A. Watson, CHP, Chief Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery, and Waste Programs Office of Nuclear Material Safety and Safeguards Docket Nos. 50-361 and 50-362

Attachment:

Supplemental Information Regarding the CSLC Responses to the City of Laguna Beachs Comments on the Scope and Content of the EIR for the SONGS Decommissioning Project cc: electronic Distribution via Listserv Additional hard copies to:

Mr. Thomas J. Palmisano Vice President, Chief Nuclear Officer Southern California Edison Co.

San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128 Mr. John Pietig City Manager City of Laguna Beach 505 Forest Avenue Laguna Beach, CA 92651

Supplemental Information Regarding the CSLC Responses to the City of Laguna Beachs Comments on the Scope and Content of the EIR for the SONGS Decommissioning Project CSLC Responses to Comments from the City of Laguna Beach (City)

In Appendix C of the Draft EIR for the SONGS decommissioning project, the CSLC has identified the Citys August 12, 2016, letter as Comment Set 7 and has identified seven specific comments within the letter. The CSLC has designated these seven comments from the Citys letter as #7-1 to #7-7. The NRC staff appreciates the CSLCs specific responses to comments #7-1 to #7-7 and concurs with them. In addition, the NRC staff recommends that the CLSC comment responses be further supplemented as follows:

1. Role of the NRC The NRCs mission is set forth in its organic statutory authority, the Atomic Energy Act of 1954, as amended (AEA).1 Under the AEA, the NRC is charged with regulating the civilian use of radioactive material. Thus, the NRCs regulatory program concerns protecting human health and property from the dangers of radioactivity that could potentially arise from such civilian use, and for ensuring the physical security of radioactive material under the ownership or control of its licensees. The NRC accomplishes its mission through a comprehensive radiation protection program for both members of the public and occupational workers (e.g., workers at a nuclear power plant). The NRC regulates its licensees through regulation, license terms and conditions, and through a robust inspection and enforcement program.2 The NRC also provides extensive guidance documents to assist its licensees with regulatory compliance. The construction and operation of a nuclear power plant, and the associated use and possession of radioactive material at the plant requires a facility operating license from the NRC.3 Once licensed, the NRC is responsible for ensuring that a nuclear power plant licensee meets the applicable NRC radiation protection requirements, including those set forth in the NRCs 10 CFR Part 20 and 50 regulations, and maintains the required level of physical security and emergency preparedness for the licensed site and the radioactive material under its control.

The NRC, however, is not responsible for operating the plant; nor does the NRC own or otherwise control the radioactive material on site. Likewise, the NRC does not hold any real property interest in the licensed site itself; nor does it have any land management authority over the site. In addition, the NRC has no role in the ultimate disposition or use of the site after the facility operating license is terminated.

The regulation of non-radioactive material or non-radioactive pollutants at a nuclear power plant is also outside the scope of the NRCs regulatory authority. Further, the NRC only has regulatory authority over those portions of a nuclear power plant that contain or process radioactive material or have a role in the nuclear fission (electricity generating) process, such as the buildings housing the reactor vessel, the spent fuel pool, and the control room. Other than 1 42 [United States Code] U.S.C. §§ 2011 et seq.

2 The NRCs general radiation protection regulations, applicable to all licensees, are set in Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Standards for Protection Against Radiation. The NRCs regulations concerning the licensing of nuclear power plants like SONGS, including decommissioning, are set forth in 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities.

3 42 U.S.C. § 2133.

Attachment

ensuring that the licensee meets the requisite physical security requirements for the facility, or those requirements concerning the transport of radioactive material into and out of the licensed facility, the NRC does not have regulatory authority over the licensees visitor center, administrative office spaces, cafeteria, roads, parking lots, daycare centers, and other buildings and structures that have no role in either holding, storing, or processing radioactive material.

In this regard, the NRC is not the only regulator of a nuclear power plant facility; several other federal, state, and local agencies typically have regulatory or permitting roles. For example, the licensee must meet the requirements of the Clean Water Act, requiring the licensee to obtain a National Pollutant Discharge Elimination System (NPDES) permit from either the United States Environmental Protection Agency (EPA), or if delegated by the EPA, the appropriate state agency. To the extent there are wetlands on the licensed site, the licensee must obtain the appropriate permit from the United States Army Corps of Engineers. The licensee must satisfy the requirements of all applicable state and local health, safety, and environmental protection lawsthose laws are implemented and enforced by the applicable state agencies. Finally, the licensee must satisfy all local or municipal zoning ordinances.

Role of the NRC During Decommissioning and License Termination In terms of decommissioning, the nuclear power plant licensee must first certify to the NRC that it has permanently stopped operating (i.e., stopped generating electricity by nuclear fission) and that it has removed all nuclear fuel from the reactor vessel.4 The decommissioning process usually lasts several years, possibly decades, and under the applicable NRC regulation, can take up to sixty years.5 At the end of the decommissioning process, the licensee will seek to terminate its operating license. The NRC will terminate the license if the licensee demonstrates that it has reduced the residual radioactivity at the licensed site to acceptable levels, i.e., those set forth in Subpart E, Radiological Criteria for License Termination, of 10 CFR Part 20, Standards for Protection Against Radiation. SCE has informed the NRC that it intends to pursue license termination in accordance with 10 CFR 20.1402, Radiological criteria for unrestricted use.6 Section 20.1402 states, in part, A site will be considered acceptable for unrestricted use if the residual radioactivity that is distinguishable from background radiation results in a [total effective dose equivalent]7 to an average member of the critical group8 that does not exceed 25 mrem (0.25 mSv) per year, including that from groundwater 4 10 CFR 50.82(a)(1)(i)-(ii).

5 10 CFR 50.82(a)(3).

6 As explained in item 3 below, SCE will continue to operate one small portion of its current licensed site, the independent spent fuel storage installation (ISFSI), indefinitely. Thus, the SCE operating license will, in effect, be reduced to the area of the ISFSI upon successful completion of the decommissioning process for the remainder of the licensed site.

7 Total effective dose equivalent or TEDE, is defined as the sum of the effective dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures). 10 CFR 20.1003. The terms effective dose equivalent and committed effective dose equivalent are also defined in 10 CFR 20.1003, which is the definitions section for 10 CFR Part 20.

8 Critical group is defined as group of individuals reasonably expected to receive the greatest exposure to residual radioactivity for any applicable set of circumstances. 10 CFR 20.1003.

sources of drinking water, and the residual radioactivity has been reduced to levels that are as low as reasonably achievable (ALARA).9 Thus, whether the licensee has demonstrated to the NRC that it has reduced the sites level of residual radioactivity to the standard specified in 10 CFR 20.140210 is the only factor that the NRC considers in determining whether the license can be terminated.11 Ensuring that the licensee safely meets the regulatory level of residual radioactivity for license termination is the goal of decommissioning. In this regard, decommissioning itself is the process by which the licensee reduces the sites residual radioactivity to the regulatory level by removing or otherwise mitigating on-site radiological contamination.12 Thus, the presence of non-radioactive contaminants on the site (e.g., PCBs, asbestos, lead-based paint), and the remediation or mitigation of such non-radiological hazards, are beyond the scope of the NRCs regulatory authority. Similarly, whether the licensee dismantles and demolishes the facilitys buildings and structures, or chooses to leave them standing as part of the decommissioning process, is not within the NRCs purview. The NRCs regulatory objective is that the licensee meets all applicable NRC public and occupational radiological safety requirements throughout the decommissioning process, and that at the completion of that process the licensee is able to demonstrate the requisite level of residual radioactivity.

2. Environmental Impacts of Decommissioning have been Previously Analyzed and are Not Significant In its August 12, 2016, letter, the City asserts that the NRC must analyze the site-specific radiological safety concerns associated with the SONGS decommissioning project in a site-specific NEPA document, and that the agencys generic NEPA decommissioning analyses are not sufficient. The analyses conducted by the NRC in support of the decommissioning of nuclear power reactors are set forth in the Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, NUREG-0586 (1988), as supplemented and updated by the Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, NUREG-0586, Supplement 1 (2002) (collectively, the Decommissioning GEIS).13 As explained below, the NRC disagrees with these assertions.

9 10 CFR 20.1402 (alteration added). The term ALARA is defined in 10 CFR 20.1003 and the NRCs ALARA requirements are generally defined in 10 CFR 20.1101, Radiation protection programs.

10 The NRC defines residual radioactivity as radioactivity in structures, materials, soils, groundwater, and other media at a site resulting from activities under the licensee's control. This includes radioactivity from all licensed and unlicensed sources used by the licensee, but excludes background radiation. It also includes radioactive materials remaining at the site as a result of routine or accidental releases of radioactive material at the site and previous burials at the site, even if those burials were made in accordance with the provisions of 10 CFR part 20. 10 CFR 20.1402.

11 As explained in item 3 below, the SCE operating license will be reduced to the area of the ISFSI and will remain in effect, indefinitely, for the ISFSI only. The NRC will apply the 10 CFR 20.1402 residual radioactivity standard in determining whether the SONGS licensed site, except for the ISFSI, can be released for unrestricted use (i.e., released from the NRC license and hence, from NRC regulatory authority).

12 The NRC defines the term decommission as to remove a facility or site safely from service and reduce residual radioactivity to a level that permits(1) Release of the property for unrestricted use and termination of the license; or (2) Release of the property under restricted conditions and termination of the license. 10 CFR 50.2, Definitions.

13 The GEIS is considered generic in that it evaluates impacts from decommissioning activities common to a number of nuclear power facilities. NUREG-0586, Supp. 1, at xi, n. (a); available at ADAMS Accession No. ML023500395.

1996 Decommissioning Rulemaking In the preamble to the 1996 rulemaking that promulgated the NRCs current nuclear power plant decommissioning regulation (10 CFR 50.82, Termination of license), the NRC described its finding that nuclear power plants undergoing decommissioning present much lower radiological safety risks than operating nuclear power plants, primarily because nuclear fission is no longer occurring in the reactor vessel and all nuclear fuel assemblies have been permanently removed from the reactor vessel and placed into the facilitys spent fuel pool.14 Specifically, the NRC found that the activities performed by the licensee during decommissioning do not have a significant potential to impact public health and safety and [therefore] require considerably less oversight by the NRC than during power operations.15 Additionally, the systems and processes required to safely maintain a decommissioning plant are much simpler than those required to run an operating plant.16 For example, unlike an operating plant, a decommissioning plant will not draw in large quantities of cooling water, which after being run through the plant systems and processed as needed, is then released back into the environment. The gaseous and liquid radioactive effluents of a decommissioning plant, to the extent that there are any, will also be far more limited than those of an operating plant. The NRC determined that any environmental impacts were expected to be minor and that [a]ny site impact should be bounded by the impacts evaluated by previous applicable GEISs as well as any site-specific [environmental impact statement (EIS)].17 NRCs NEPA Compliance The NRC fulfills its NEPA obligations with respect to the decommissioning of nuclear power plants through a combination of generic and site-specific environmental analyses. The NRC prepares a site-specific EIS to support construction and operation of the plant.18 Subsequent to the issuance of the SONGS operating licenses in 1982, the NRC performed additional environmental reviews to support its decisions regarding the approval or disapproval of specific license amendment or exemption requests. The NRC documented these reviews in accordance with NEPA; specifically, the NRC staff would prepare an environmental assessment (EA) with a finding of no significant impact (FONSI).19 In addition to the analyses set forth in these site-14 61 FR 39278, Decommissioning of Nuclear Power Reactors, (July 29, 1996) at 39278-79. After several years in the spent fuel pool, spent fuel assemblies are typically removed from the pool and placed into dry storage in an ISFSI located on the site. SCE expects to transfer all spent fuel assemblies currently in the SONGS spent fuel pools to the onsite ISFSI by the end of 2018.

15 Id., at 39279 (alteration added).

16 Id.

17 Id., at 39283 (alteration added).

18 The results of the environmental reviews are typically provided as a NUREG document for each facility; NUREG-0490, Final Environmental Statement related to the operation of San Onofre Nuclear Generating Station, Units 2 and 3", dated April 1981 (ADAMS Accession No. ML18239A414), is the EIS supporting the NRCs decision to issue the operating licenses for the SONGS, Units 2 and 3, facilities.

19 E.g., 61 FR 50513 (September 26, 1996) (EA/FONSI for amendments of operating licenses to allow an increase in fuel enrichment); 66 FR 32964 (June 19, 2001) (EA/FONSI for amendments of operating licenses to allow SCE to increase its maximum reactor core power level for both Units 2 and 3); 80 FR 21271 (April 17, 2015)

(EA/FONSI for issuance of an exemption from emergency planning requirements due to SONGS being in a decommissioning status).

specific NEPA documents, some of which may remain applicable through the decommissioning process,20 the decommissioning of SONGS is covered by the Decommissioning GEIS.

The Decommissioning GEIS is a comprehensive generic EIS that covers the potential environmental impacts likely to arise during decommissioning.21 The NRCs prior operational experience served as the basis for the 1988 Decommissioning GEIS, and was supplemented with additional experience in conducting decommissioning during the 2002 update of the Decommissioning GEIS. The NRC has found that most potential environmental impacts resulting from decommissioning are common to all nuclear power plants and therefore, can be analyzed generically. Additionally, for all environmental impacts dispositioned generically, the NRC has found that decommissioning activities will have only small impacts (i.e., impacts that are not significant under NEPA). Therefore, decommissioning is not a major Federal action under NEPA.22 In short, the NRC considers decommissioning activities to present such low safety and environmental risks that the only licensee decommissioning action triggering a required NRC decision (and as such, triggering a site-specific NEPA review) under 10 CFR 50.82 is the submission of a license termination plan (LTP), which the licensee is required to submit at least two years before the expected license termination date.23 Thus, if a licensee does not submit any other license amendment or exemption requests during decommissioning, the only site-specific NRC NEPA review will be the one conducted for the LTP.

Since the Decommissioning GEIS was supplemented and updated in 2002, the NRCs operational experience has continued to show that the extensive, detailed analyses set forth in the Decommissioning GEIS will bound or account for most reasonably foreseeable, potential environmental impacts that may arise at any decommissioning plant, including SONGS.24 As long as the licensees decommissioning activities remain within the scope of the Decommissioning GEISs analyses, or applicable site-specific NEPA analyses conducted in support of previous licensing actions, those activities will be bounded and the potential impacts will be considered to be previously analyzed and not significant for NEPA purposes.

The review of those potential site-specific decommissioning environmental impacts (i.e., those not dispositioned generically in the Decommissioning GEIS) are first addressed in the 20 For example, the June 2001 EA/FONSI analyzed the increase to water temperature resulting from the proposed increase of the maximum reactor core power level. The temperature increase would impact the cooling water discharged into the Pacific Ocean. As the increase in water temperature was within the limit on differential temperature allowed by the California Regional Water Quality Control Board, the increase was not found to be a significant environmental impact. As a decommissioning plant does not need water to cool its reactor, this EA/FONSI bounds any impacts to water temperature (at least with respect to temperature increases) arising from the SONGS decommissioning process, and complements the findings in the Decommissioning GEIS.

21 In adjudicating a challenge to the NRCs use of generic NEPA analyses, the United States Supreme Court held that [t]he generic method chosen by the agency is clearly an appropriate method of conducting the hard look required by NEPA. Baltimore Gas and Electric Co., v. Natural Resources Defense Council, 462 U.S. 87, 101 (1983).

22 Council on Environmental Quality (CEQ) regulations define the terms Major Federal action and Significantly.

40 CFR 1508.18 and 1508.27. The NRC has adopted these CEQ definitions. 10 CFR 51.14(b).

23 10 CFR 50.82(a)(9) (LTP requirements); 10 CFR 50.82(a)(10) (NRC approval requirements). During its review of the LTP, the NRC will prepare a safety evaluation and an EA, and if approved, the NRC will incorporate the LTP into the operating license via a license amendment.

24 As of August 2018, the NRC has overseen the successful decommissioning of ten nuclear reactor units and is currently overseeing the decommissioning of twenty reactor units (several nuclear power plants, such as SONGS, have more than one reactor unit).

construction and operation EIS (in the case of SONGS, NUREG-0490, referenced above).25 Additionally, such site-specific impacts would have been analyzed in the EA/FONSIs for license amendment or exemption requests during the plants operation, such as those referenced above. Finally, during decommissioning, these site-specific impacts will be analyzed by the NRC staff in the appropriate NEPA document (most likely an EA but if necessary, an EIS) in the event the licensee submits a license amendment or exemption request, or after the licensee submits the license amendment request to approve the LTP.26 10 CFR 50.82 The NRCs NEPA compliance is supported by the requirements of 10 CFR 50.82. Section 50.82 prohibits a licensee from performing any decommissioning activity that would result in significant environmental impacts not previously reviewed.27 This provision was added by the 1996 rule [t]o account for site-specific situations that may occur outside these environmental impact considerations; the intent of this provision was to prohibit decommissioning activities that could result in significant environmental impacts not previously reviewed.28 The licensee is also required to submit to the NRC a post-shutdown decommissioning activities report (PSDAR), which is one of the regulatory prerequisites that must be satisfied before a licensee may begin decommissioning.29 The NRC does not approve or disapprove the PSDAR; the submission of a PSDAR is a licensee reporting requirement. As such, the submission of the PSDAR does not result in an agency action. As there is no agency action, there is no requirement to perform a NEPA analysis on the licensees PSDAR submission. The licensee, however, must include in the PSDAR a discussion that provides the reasons for concluding that the environmental impacts associated with site-specific decommissioning activities will be bounded by appropriate previously issued environmental impact statements.30 Although not approved, the NRC staff will still review the PSDAR and to extent that the NRC has concerns with the PSDARs environmental compliance discussion or other required portions of the PSDAR, the NRC staff may request additional information from the licensee. Further, 10 CFR 50.82 requires a licensee to inform the NRC and affected States, in writing, before performing any decommissioning activity inconsistent with, or making any significant schedule change from, those actions and schedules described in the PSDAR.31 Thus, if the licensee wishes to perform a decommissioning activity that would result in a significant impact not previously reviewed, the licensee would be required to submit a license 25 E.g., NUREG-0490, § 5.2, Impacts on Land Use, § 5.4.1, Environmental Impacts/Terrestrial Environment,

§ 5.4.2, Environmental Impacts/Impacts on the Aquatic Environment, § 5.5.2, Radiological impacts on biota other than man, § 9.4, Decommissioning, and Appendix D, Cultural Resources.

26 Any site-specific NEPA analysis prepared during decommissioning will rely on the Decommissioning GEIS analyses for the generically dispositioned issues. In this regard, the site-specific NEPA analysis tiers off the Decommissioning GEIS. 40 CFR 1502.20 and 1508.28 (CEQ regulations); 10 CFR Part 51, Appendix A, 1(b)

(adopted by NRC).

27 10 CFR 50.82(a)(6)(ii).

28 61 FR, at 39283.

29 10 CFR 50.82(a)(4)(i). Prior to the 1996 rule, licensees were required to submit a decommissioning plan, which was subject to NRC approval. The 1996 rule replaced the decommissioning plan with the PSDAR. 61 FR at 39279 (A major change from the current rule is that power reactor licensees would no longer be required to have an approved decommissioning plan before being permitted to perform major decommissioning activities).

30 10 CFR 50.82(a)(4)(i).

31 10 CFR 50.82(a)(7).

amendment request or an exemption request. The NRC would then analyze the proposed action and prepare the necessary site-specific NEPA analysis. If the licensee wishes to perform a decommissioning activity that is otherwise inconsistent with the PSDAR, the licensee would be required to notify the NRC and affected States in writing before taking any action. The NRC and affected States would then have the opportunity to review the proposed action and request additional information from the licensee before the action is taken.

Preparation of a Joint EIR/Environmental Impact Statement (EIS)

In its August 12, 2016, letter, the City asserts that the NRC and the CSLC should prepare a joint EIR. In response, the NRC staff does not agree that it should prepare a joint EIR/EIS with CSLC (nor does the NRC need to prepare a stand-alone EIS). According to the draft EIR, the jurisdiction of the CSLC is seaward of the ordinary high-water mark.32 The proposed CSLC action concerns the disposition of submerged lands leased to SCE and the City of Riverside, California,33 and the improvements thereon, namely, the SONGS, Units 2 and 3, offshore intake and discharge conduits and associated appurtenances, navigational and environmental monitoring buoys, and riprap along shore seaward of the ordinary high-water mark.34 Whether these improvements should remain in place indefinitely or be partially or wholly removed is a question that is not within the NRCs regulatory authority. As with any part of the NRC-licensed SCE site, the NRCs regulatory objective is that SCE be able to demonstrate that it has met the 10 CFR 20.1402 level of residual radioactivity at the conclusion of the decommissioning process.

SONGS PSDAR In its August 12, 2016, letter, the City states that it disagrees with the conclusion reached by SCE in its PSDAR, submitted in September 2014 (ADAMS Accession No. ML14269A033). In its PSDAR, SCE stated that [b]ased on current plans, no decommissioning activities unique to the site have been identified and no activities or environmental impacts outside the bounds considered in the GEIS have been identified.35 By letter dated August 20, 2015 (ADAMS Accession No. ML15204A383), the NRC acknowledged receipt of SCEs PSDAR, documented the review, and summarized comments received during the PSDAR public meeting held near the SONGS site in October 2014. In its August 20, 2015, letter, the NRC staff stated:

[SCE] compared the SONGS, Units 2 and 3, facility to the reference facility in NUREG-0586 and found that the SONGS, Units 2 and 3, environmental impacts were bounded by the analysis provided in NUREG-0586. After reviewing [SCEs]

comparison, the NRC staff finds that the potential environmental impacts associated with SONGS, Units 2 and 3, decommissioning activities are bounded by the previously issued GEIS and its [supplement], are described consistent 32 CSLC, Draft Environmental Impact Report for the San Onofre Nuclear Generating Station (SONGS) Units 2 & 3 Decommissioning Project, State Clearinghouse No. 2016071025, CSLC EIR No. 784 (June 2018) at ES-3.

33 The City of Riverside is not an NRC licensee and the NRC has no regulatory authority over the City of Riverside.

34 Id., at ES-1.

35 SCE, PSDAR (September 23, 2014) at 8.

with the guidance in RG 1.185,36 and meet the requirements of 10 CFR 50.82(a)(4)(i).37 The City has provided no information that any of the potential environmental impacts that may result from the planned decommissioning activities, as described in SCEs September 2014 PSDAR, are beyond the scope of the Decommissioning GEIS and other previously prepared NRC site-specific NEPA documents or are, in any other way, significant. In response to the Citys assertion that the NRC must analyze the site-specific radiological safety issues, presumably in an EIS, the analyses provided in the Decommissioning GEIS are sufficient and bound any reasonably foreseeable impact.

Major Decommissioning Activities; NRC Oversight During Decommissioning The NRC makes a distinction between an environmental issue, which is analyzed under NEPA, and a safety issue, for which the NRC is responsible under the AEA. Safety issues are analyzed in NRC safety reports, such as a nuclear power plants final safety analysis report or FSAR, which is part of the plants licensing basis, and is updated on a regular basis. Any changes that may impact the safety of the plant are evaluated by the NRC staff as part of the safety evaluation reports that accompany licensee requests for the approval of a license amendment or exemption request, or are otherwise reviewed by the NRC staff as part of the licensee reporting and NRC inspection processes. As a safety agency, the NRC handles safety issues as they arise on an ongoing and operational basis.

A licensee is prohibited from engaging in major decommissioning activities until ninety days after the submission of the PSDAR, provided that the licensee has submitted its 10 CFR 50.82(a)(1)(i)-(ii) certifications that it has permanently ceased operations and has removed all fuel assemblies from the reactor vessel.38 Once the post-PSDAR ninety day period has run and the requisite certifications have been submitted to the NRC, the licensee may begin major decommissioning activities. The licensee does not need prior NRC approval to conduct such major decommissioning activities, provided that the licensees activities remain within a certain defined scope, as prescribed by 10 CFR 50.59, Changes, tests and experiments.39 During the decommissioning process, the NRC maintains comprehensive regulatory oversight over the plant. The licensee remains subject to the terms and conditions of its license, and as such, remains subject to NRC inspection and enforcement. As described in Inspection Manual Chapter (IMC) 2561, Decommissioning Power Reactor Inspection Program (ADAMS Accession No. ML17348A400), the NRC staff will engage in regular on-site inspections that 36 Regulatory Guide (RG) 1.185, Standard Format and Content for Post-Shutdown Decommissioning Activities Report, Revision 1 (June 2013) (ADAMS Accession No. ML13140A038). RG 1.185 is an NRC guidance document developed to assist licensees in complying with the PSDAR requirements.

37 NRC, Letter to T.J. Palmisano, Vice President and Chief Nuclear Officer, SCE (August 20, 2015), at 5.

38 The term major decommissioning activity means, for a nuclear power reactor facility, any activity that results in permanent removal of major radioactive components, permanently modifies the structure of the containment, or results in dismantling components for shipment containing greater than class C waste in accordance with § 61.55 of this chapter. 10 CFR 50.2.

39 Section 50.59 provides parameters by which a licensee may make certain changes to the facility without prior NRC approval. If the licensees intended action will exceed the 10 CFR 50.59 parameters, the licensee must seek NRC approval before taking the action, typically in the form of a license amendment or exemption request.

The NRC will then conduct a site-specific safety and environmental analysis (NEPA) prior to approving or disapproving the licensees proposed action.

emphasize radiological controls and management, procedure compliance, spent fuel pool operation, and the safety review program. Many activities that occur during decommissioning are routine and occur frequently in operating plants. These include decontamination of surfaces and components, surveys for radioactive contamination, waste packaging and disposal, and other activities. During active decommissioning periods, NRC inspectors may be at the facility 2 or 3 weeks of the month in order to observe ongoing activities. During a long-term storage period, inspectors would be present to conduct inspections at least once a year in accordance with the decommissioning reactor inspection program outlined in IMC 2561.

The NRC has also issued several regulatory guidance documents for nuclear power plant decommissioning, including Regulatory Guide (RG) 1.184, Decommissioning of Nuclear Power Reactors, Revision 1 (October 2013; ADAMS Accession No. ML13144A840); RG 1.185, Standard Format and Content for Post-Shutdown Decommissioning Activities Report, Revision 1 (June 2013; ADAMS Accession No. ML13140A038)); and RG 4.21, Minimization of Contamination and Radioactive Waste Generation: Life-Cycle Planning (June 2008; ADAMS Accession No. ML080500187). The guidance is directed toward NRC licensees and provides suggested procedures and methodologies to meet the applicable NRC regulatory requirements during decommissioning. Although compliance with guidance is not required, licensees have an incentive to follow the procedures and methodologies set forth in the guidance documents as NRC practice is to presume that compliance with the guidance means that the licensee is in compliance with the applicable NRC regulation upon which the guidance is based (e.g., 10 CFR 50.82 and 10 CFR 20.1402).

Finally, the NRCs regular contact with the licensee during decommissioning, through its on-site inspection program and otherwise, allow the NRC and licensee to address, on a site-specific basis, any radiation related safety concern that may arise during the process. Based upon its operating experience, the NRC has determined that all expected and reasonably foreseeable safety issues for SONGS are bounded by the Decommissioning GEIS, the current SONGS licensing basis (e.g., the FSAR and NRC staff safety evaluations associated with various licensing actions), and can be appropriately controlled through the existing safety programs.

3. SONGS Independent Spent Fuel Storage Installation; Seismic Concerns The Citys August 12, 2016, letter raises concerns about the radiological safety impacts of spent fuel storage casks, specifically in regard to storing spent fuel in a seismically active marine environment.40 As explained below, the NRC staff has determined that the storage of spent fuel, in storage casks, at SONGS meets all applicable NRC safety criteria.

Reduction of SONGS License to the ISFSI The NRC issued to SCE the SONGS operating licenses in accordance with its regulations in 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. As a Part 50 license holder, SCE holds a general license to install and operate an independent spent fuel 40 City of Laguna Beach, Letter to C. Herzog, Senior Environmental Scientist, CSLC and M. Vaaler, Project Manager, NRC (August 12, 2016), at 3, n. 8.

storage installation or ISFSI, on the SONGS site.41 An ISFSI consists of a large concrete structure to safely store the spent fuel. The spent fuel assemblies are contained in the storage casks that are placed on or within the concrete structure of the ISFSI; the casks can consist of one or more cask designs, all of which must have been approved by the NRC.42 The storage casks are passive systems; they are designed with one purpose, to safely store spent fuel. In addition to the concrete structure and storage casks, an ISFSI is typically fenced or otherwise secured as it is required to be located in a restricted access area.

The SONGS ISFSI is not included in the scope of the current SONGS decommissioning project and in all likelihood, will not be included in the LTP when submitted to the NRC. Thus, the aim of the current decommissioning process is to satisfy the requirements of 10 CFR 20.1402 for all areas of SONGS except the ISFSI. After the NRC approves the SONGS LTP, and SCE has completed the current decommissioning process and demonstrated its compliance with 10 CFR 20.1402, the NRC will amend SCEs Part 50 facility operating license such that the license will be reduced to an area that only encompasses the ISFSI facility. At that point, the only remaining licensee activities that are permitted and regulated by the NRC are those related to spent fuel storage and the eventual decommissioning of the ISFSI itself, once the spent fuel has been permanently removed from the ISFSI.43 ISFSI Design and Operation During the period of ISFSI operation, the SONGS ISFSI will continue to be governed by the NRCs general license regulations for ISFSIs in Subpart K, General License for Storage of Spent Fuel at Power Reactor Sites, of 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste. The NRCs regulations in 10 CFR Part 72 provide requirements for the safe design and operation of ISFSIs. Any operational conditions, required actions, monitoring or surveillance requirements, or other technical specifications that are needed for safe operation of the casks located at a general license ISFSI are included in the certificate of compliance that the NRC issues to the cask manufacturer. Section 72.212 requires licensees to comply with the terms, conditions, and specifications of the cask certificate.44 In particular, the licensee must perform written evaluations before use of a given cask system that demonstrate that

[c]ask storage pads and areas have been designed to adequately support the static and dynamic loads of the stored casks, considering potential amplification of earthquakes through soil-structure interaction, and soil liquefaction potential or other soil instability due to vibratory ground motion.45 41 Under the applicable NRC regulations in 10 CFR Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste, the general ISFSI license is incident to the Part 50 license. The applicable regulation, 10 CFR 72.210, General license issued, states that [a] general license is hereby issued for the storage of spent fuel in an independent spent fuel storage installation at power reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50 or 10 CFR part 52. The conditions of the general ISFSI license are set forth in 10 CFR 72.212, Conditions of general license issued under § 72.210.

42 10 CFR 72.212(b)(2)-(3); 10 CFR 72.214, List of approved spent fuel storage casks.

43 As a general license ISFSI, the SONGS ISFSI will be decommissioned in accordance with 10 CFR 50.82.

44 10 CFR 72.212(b)(3).

45 10 CFR 72.212(b)(5)(ii) (alteration added).

Such written evaluations are subject to NRC inspection.

NRC regulations also require general ISFSI licensees to conduct radiation monitoring to ensure compliance with the NRC requirements for radiation dose limits for the public and ISFSI workers.46 The NRC maintains oversight of ISFSIs, and the agency staff routinely inspects the site operations to ensure continued compliance with all applicable regulatory requirements, including the conditions and specifications of the applicable cask certificates.

In addition, the NRC requires aging management programs for spent fuel storage casks as storage operations continue into a renewed storage term.47 Aging management programs include monitoring and inspections of both the ISFSI support structure and storage casks to detect any degradation, and corrective actions (such as further inspections, repairs or replacement of components, and other mitigation measures) to ensure that the ISFSI continues to meet the NRCs requirements for safe spent fuel storage. Licensees assess the effectiveness of these programs on an ongoing basis to determine if they need to be adjusted to address unexpected degradation, or degradation that may be occurring at a greater rate than was initially assumed. The NRCs oversight of ISFSIs includes inspection of a licensees aging management activities.

Operating experience from the ISFSIs currently in operation is continually assessed by the licensees and the NRC to determine if new information, knowledge, and experience warrant any changes to licensed spent fuel storage operations. If a potential environmental impact (e.g.,

increased seismic activity) that could adversely affect the safe operation of the ISFSI is identified, the NRC will determine if the licensee will need to reevaluate its analyses and associated spent fuel storage operations to address the identified change.

Seismic Issues In its development of the 2002 update to the Decommissioning GEIS, the NRC staff considered various site-specific issues at SONGS, including seismic risks. A draft was made available for public comment and one SONGS-specific comment was received. The comment stated, SONGS is located in a highly active seismic zone, where seismic activity is speculated by some geological experts to generate quakes up to 7.6 Magnitude on the Richter Scale (by new evidence of local off-shore blind thrust faults, which cause a greater extent of groundshaking and acceleration than the manner in which quakes are traditionally studied). SONGS was only designed and constructed to withstand a maximum quake of 7.0 Magnitude. SONGS is located in an area immediately on the southern California coastline, with most facilities elevated only to a level of 20 ft. above mean sea level. These facilities are highly exposed and vulnerable to effects of rising sea levels, and tsunamis, and are insufficiently protected.48 46 10 CFR 72.104, Criteria for radioactive materials in effluents and direct radiation from an ISFSI or [monitored retrieval storage] MRS; 10 CFR 72.106, Controlled area of an ISFSI or MRS. Both sections 72.104 and 72.106 are made applicable to general ISFSI licenses by operation of paragraph (c) of 10 CFR 72.13, Applicability.

47 10 CFR 72.240, Conditions for spent fuel storage cask renewal.

48 Decommissioning GEIS, NUREG-0586, App. O (2002) at O-124.

In response, the NRC replied, NRC staff recognizes that there is wide variability among nuclear power plants.

However, based on the results of our analysis, the impacts resulting from decommissioning are similar regardless of plant characteristics, including site-specific information from San Onofre. The NRC established an envelope of environmental impacts resulting from decommissioning activities, identified those activities that can be bounded by a generic evaluation, and identified those that require a site-specific analysis. The NRC concentrated the environmental analysis on those activities with the greatest likelihood of having an environmental impact. Even for those impacts that have been determined to be generic, a licensee is required to do a site-specific analysis [in the PSDAR] to determine whether the impacts fall within the generic envelope. If they are outside of the bounds of the generic envelope, the licensee must seek approval from the NRC.49 The NRC is aware of no information, and the City has not provided any, that would invalidate the NRCs environmental and safety analyses, as set forth in the Decommissioning GEIS with respect to seismic activity or any other issue.

49 Id., at O-124 to O-125.

ML17081A511 *via email OFFICE NMSS/RDB/PM NMSS/DUWP/LA OGC NMSS/RDB/BC NAME MVaaler CHolston APessin* BWatson DATE 3/21/2017 4/2/2017 9/4/2018 9/5/2018