Holtec Requests NRC Approve Sale of Pilgrim Site by End of 2019

Seeks to Complete Decommissioning Decades Earlier

On November 16, 2018, Entergy Corporation and Holtec International, through their affiliates, asked the U.S. Nuclear Regulatory Commission (NRC) to approve the sale of the Pilgrim Nuclear Power Station to Holtec after shutdown.  According to the associated press release, doing so would allow Holtec to complete decommissioning and site restoration decades sooner than if Entergy completed decommissioning.

OverviewThe companies jointly filed a License Transfer Application, requesting approval for the transfer of the Pilgrim Nuclear Power Station, as well as its Nuclear Decommissioning Trust Fund, to Holtec after the plant permanently shuts down by June 1, 2019.  They also made detailed separate filings that lay out the process each company would use to decommission the facility.

In order to facilitate a timely transaction closing by the end of 2019, the companies have asked the NRC to approve the application by May 31, 2019.  According to the press release, doing so will benefit the community, employees and other interested constituents.

Holtec’s filings describe the plan of its subsidiary, Holtec Decommissioning International, to complete the dismantling, decontamination and remediation of Pilgrim to NRC standards within eight years of license transfer (i.e., by the end of 2027) assuming timely regulatory approvals.  According to the press release, Holtec’s process will achieve site restoration decades sooner than if Entergy retained the plant while meeting all applicable local, state and federal regulations.

Holtec estimates total costs for decommissioning Pilgrim at $1.13 billion.  As of October 31, 2018, the balance in Pilgrim’s Decommissioning Trust Fund was $1.05 billion.

Holtec has contracted with Comprehensive Decommissioning International, LLC (CDI) to perform the decommissioning, including demolition and site cleanup.  CDI is a joint venture company of Holtec International and SNC-Lavalin.  According to the press release, “The decommissioning experience held by Holtec and SNC-Lavalin gives CDI more than half a century of managing complex projects in both the commercial and government nuclear sectors worldwide.”

Project Highlights

The completion of decommissioning will result in the release of all portions of the site from the current NRC license, with the exception of the Independent Spent Fuel Storage Installation (ISFSI) – the area where spent nuclear fuel is stored in dry casks until the U.S. Department of Energy (DOE) transfers the spent fuel offsite.

As part of its plan, Holtec expects to move all spent nuclear fuel into dry casks within three years following plant shutdown.  Additionally, Holtec has a pending application with the NRC for a Consolidated Interim Storage Facility (CISF) in New Mexico, which could eventually store spent nuclear fuel from Pilgrim and other U.S. nuclear power plants.


The Pilgrim Nuclear Power Station employs about 600 nuclear professionals and generates 680 megawatts of virtually carbon-free electricity, enough to power more than 600,000 homes.  Pilgrim began generating electricity in 1972.  Entergy purchased the plant in 1999 from Boston Edison.

Entergy Corporation is an integrated energy company engaged primarily in electric power production and retail distribution operations.  Entergy owns and operates power plants with approximately 30,000 megawatts of electric generating capacity, including nearly 9,000 megawatts of nuclear power.  Entergy delivers electricity to 2.9 million utility customers in Arkansas, Louisiana, Mississippi and Texas.  Entergy has annual revenues of approximately $11 billion and more than 13,000 employees.

Holtec International is a privately held energy technology company with operation centers in Florida, New Jersey, Ohio and Pennsylvania in the United States.  Globally, Holtec International has operation centers in Brazil, Dubai, India, South Africa, Spain, the United Kingdom and Ukraine.  Holtec’s principal business concentration is in the nuclear power industry.  Since the 1980s, Holtec has been densifying wet storage in nuclear plants’ spent fuel pools, which defers the need for and expense of alternative measures by as much as two decades.  Holtec has done this at over 110 reactor units in the United States and abroad.  Holtec also offers services regarding dry storage and transport of nuclear fuel.  Holtec is working to develop the world’s first below-ground CISF in New Mexico and a 160-Megawatt walk away safe small modular reactor, SMR-160.  The SMR-160 is developed to bring cost competitive carbon-free energy to all corners of the earth including water-challenged regions.  Holtec is also a major supplier of special-purpose pressure vessels and critical-service heat exchange equipment such as air-cooled condensers, steam generators, feedwater heaters and water-cooled condensers.  Virtually all products produced by Holtec are built in its three large manufacturing plants in the United States and one in India.

For additional information about the Pilgrim plant, please go to www.pilgrimpower.com.  Additional information about Entergy is available at www.entergy.com.  To learn more about Holtec International, please visit www.holtecinternational.com.  

DOE Seeks Public Comment re Interpretation of High-Level Radioactive Waste

On October 10, 2018, the U.S. Department of Energy (DOE or Department) issued a Federal Register notice seeking public comment on the Department’s interpretation of the definition of the statutory term “high-level radioactive waste” (HLW) as set forth in the Atomic Energy Act of 1954 and the Nuclear Waste Policy Act of 1982.

DOE interprets the term “high-level radioactive waste,” as stated in the Atomic Energy Act of 1954 as amended (AEA) and the Nuclear Waste Policy Act of 1982 as amended (NWPA), in a manner that defines DOE reprocessing wastes to be classified as either HLW or non-HLW based on the radiological characteristics of the waste and their ability to meet appropriate disposal facility requirements.  The basis for DOE’s interpretation comes from the AEA and NWPA definition of HLW:

  1. the highly radioactive material resulting from the reprocessing of spent nuclear fuel, including liquid waste produced directly in reprocessing and any solid material derived from such liquid waste that contains fission products in sufficient concentrations; and,
  1. other highly radioactive material that the Commission, consistent with existing law, determines by rule requires permanent isolation.

In paragraph A, according to the Federal Register notice, Congress limited HLW to those materials that are both “highly radioactive” and “resulting from the reprocessing of spent nuclear fuel.”  Reprocessing generates liquid wastes, with the first cycle of reprocessing operations containing the majority of the fission products and transuranic elements removed from the spent nuclear fuel (SNF).  Thus, in paragraph A, Congress distinguished HLW with regard to its form as both “liquid waste produced directly in reprocessing” and “any solid material derived from such liquid waste that contains fission products in sufficient concentrations,” states the Federal Register notice.

In paragraph B, Congress defined HLW also to include “other highly radioactive material” that the U.S. Nuclear Regulatory Commission (NRC) determines by rule “requires permanent isolation,” continues the Federal Register notice.  HLW under paragraph B includes highly radioactive material regardless of whether the waste is from reprocessing or some other activity.  Further, under paragraph B, classification of material as HLW is based on its radiological characteristics and whether the material requires permanent isolation, states the Federal Register notice.

According to the Federal Register notice, the common element of these statutory paragraphs defining HLW is the requirement and recognition that the waste be “highly radioactive.”  Additionally, both paragraphs reflect a primary purpose of the NWPA, which is to define those materials for which disposal in a deep geologic repository is the only method that would provide reasonable assurance that the public and the environment will be adequately protected from the radiological hazards the materials pose.

The terms “highly radioactive” and “sufficient concentrations” are not defined in the AEA or the NWPA.  By providing in paragraph A that liquid reprocessing waste is HLW only if it is “highly radioactive” and that solid waste derived from liquid reprocessing waste is HLW only if it is “highly radioactive” and contains fission products in “sufficient concentrations” without further defining these standards, the Federal Register notice asserts that Congress left it to DOE to determine when these standards are met.  Given Congress’ intent that not all reprocessing waste is HLW, the Federal Register notice states that it is appropriate for DOE to use its expertise to interpret the definition of HLW, consistent with proper statutory construction, to distinguish waste that is non-HLW from waste that is HLW.

The DOE interpretation is informed by the radiological characteristics of reprocessing waste and whether the waste can be disposed of safely in a facility other than a deep geologic repository.  The Federal Register notice explains that this interpretation is based upon the principles of the NRC’s regulatory structure for the disposal of low-level radioactive wastes.

In its regulations, NRC has identified four classes of low-level radioactive waste (LLW) — Class A, B or C — for which near-surface disposal is safe for public health and the environment, as well as Greater-than-Class C (GTCC) low-level radioactive waste for which near-surface disposal may be safe for public health and the environment.  This waste classification regime is based on the concentration levels of a combination of specified short-lived and long-lived radionuclides in a waste stream, with Class C LLW having the highest concentration levels.  Waste that exceeds the Class C levels is evaluated on a case-specific basis to determine whether it requires disposal in a deep geologic repository or whether an alternative disposal facility can be demonstrated to provide safe disposal.  According to the Federal Register notice, the need for disposal in a deep geologic repository results from a combination of two radiological characteristics of the waste:  (1) high activity radionuclides, including fission products, which generate high levels of radiation; and, (2) long-lived radionuclides which, if not properly disposed of, would present a risk to human health and the environment for hundreds of thousands of years.

Because the NRC has long-standing regulations that set concentration limits for radionuclides in waste that is acceptable for near-surface disposal, the Federal Register notice contends that it is reasonable to interpret “highly radioactive” to mean, at a minimum, radionuclide concentrations greater than the Class C limits.  Reprocessing waste that does not exceed the Class C limits is non-HLW.

DOE interprets “sufficient concentrations” in the statutory context in which the definition was enacted, which is focused on protecting the public and the environment from the hazards posed by nuclear waste.  In addition to the characteristics of the waste itself, the risk that reprocessing waste poses to human health and the environment depends on the physical characteristics of the disposal facility and that facility’s ability to safely isolate the waste from the human environment.  Relevant characteristics of a disposal facility may include the depth of disposal; use of engineered barriers; and, geologic, hydrologic and geochemical features of the site.  Taking these considerations into account, the Federal Register notice states that it is reasonable to interpret “sufficient concentrations” to mean concentrations of fission products in combination with long-lived radionuclides that would require disposal in a deep geologic repository.

Accordingly, under DOE’s interpretation, solid waste that exceeds the NRC’s Class C limits would be subject to detailed characterization and technical analysis of the radiological characteristics of the waste.  This, combined with the physical characteristics of a specific disposal facility and the method of disposal, would determine whether the facility could meet its performance objectives and if the waste can be disposed of safely.  The waste characterization and analysis process would govern this approach, as well as the performance objectives for the disposal facility established by the applicable regulator, to ensure that it is protective of human health and the environment.

The DOE interpretation does not require the removal of key radionuclides to the maximum extent that is technically and economically practical before DOE can define waste as non-HLW.  According to the Federal Register notice, nothing in the statutory text of the AEA or the NWPA requires that radionuclides be removed to the maximum extent technically and economically practical prior to determining whether waste is HLW.  DOE has determined that the removal of radionuclides from waste that already meets existing legal and technical requirements for safe transportation and disposal is unnecessary and inefficient, as well as does not benefit human health or the environment.  To the contrary, the Federal Register notice states that it potentially presents a greater risk to human health and the environment because it prolongs the temporary storage of waste.

Therefore, under DOE’s interpretation, waste resulting from the reprocessing of SNF is non-HLW if the waste:

  1. does not exceed concentration limits for Class C low-level radioactive waste as set out in section 61.55 of title 10, Code of Federal Regulations; or,
  1. does not require disposal in a deep geologic repository and meets the performance objectives of a disposal facility as demonstrated through a performance assessment conducted in accordance with applicable regulatory requirements.

Reprocessing waste meeting either I or II of the above is non-HLW.  Therefore, according to the Federal Register notice, such waste may be classified and disposed in accordance with its radiological characteristics in an appropriate facility provided all applicable requirements of the disposal facility are met. 

For additional information, see 83 Federal Register 50,909 (October 10, 2018).  Interested stakeholders may also contact Theresa Kliczewski at HLWnotice@em.doe.gov or at (202) 586-3301.

License Transfer Approved for La Crosse Nuclear Plant

On May 24, 2016, the U.S. Nuclear Regulatory Commission (NRC) announced that the agency has approved the transfer of the license for the La Crosse Boiling Water Reactor from the Dairyland Power Cooperative to LaCrosseSolutions.

The La Crosse plant—which is located in Genoa, Wisconsin—has been shut down since 1987.  At that time, the NRC modified the original operating license to a possession-only license for the purpose of storage of nuclear materials and waste and decommissioning activities.

On October 8, 2015, Dairyland submitted an application to the NRC requesting transfer of the license to LaCrosseSolutions, which is a subsidiary of EnergySolutions.  The license transfer would allow LaCrosseSolutions to expedite decommissioning activities on the site.

Under the terms of the transfer, Dairyland will remain the owner of the site and retain title to and responsibility for the spent nuclear fuel, which is currently stored in dry casks on the site. LaCrosseSolutions will lease the above-ground structures (other than the spent fuel storage site) and assume responsibility for decommissioning under NRC requirements.

EnergySolutions entered into a similar arrangement as that being done for the La Crosse nuclear power plant when it began to decommission the shuttered Zion nuclear power plant in Illinois in 2010.

The NRC’s order approving the transfer and its safety evaluation of the transfer are available in the NRC’s ADAMS document database at ML16123A049.

For additional information, please contact Maureen Conley of the NRC at (301) 415-8200.

Final Supplement Issued for
 Yucca Mountain EIS

In early May 2016, the U.S. Nuclear Regulatory Commission (NRC) published the staff’s final Environmental Impact Statement (EIS) supplement on a proposed permanent repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain in Nevada.  The supplement analyzes potential impacts on groundwater and surface groundwater discharges and determines all impacts would be “small.”


The May 2016 NRC document that supplements Environmental Impact Statements that the U.S. Department of Energy (DOE) prepared on the proposed repository.  DOE issued the final EIS in 2002, then supplemented it in June 2008 when it submitted a construction authorization application to the NRC.

Under the Nuclear Waste Policy Act, the NRC is to adopt DOE’s EIS to the extent practicable.  In September 2008, NRC staff recommended adoption of DOE’s Environmental Impact Statements, but noted the need to supplement the study of groundwater effects in the Yucca Mountain aquifer beyond DOE’s analyzed location at the site boundary.  DOE ultimately deferred to the NRC to prepare the supplement.


In August 2015, NRC published a draft of the supplement for public comment.  (See LLW Notes, July/August 2016, pp. 28-29.)  During the 91-day comment period, NRC staff conducted public meetings to present the report and receive comments in Rockville, Maryland and in Las Vegas and Amargosa Valley, Nevada.

The NRC received more than 1,200 comments on the draft supplement, including comment letters and oral comments.  The NRC staff’s responses to these comments, and descriptions of changes made to the final report in response to comments, can be found in Appendix B of the supplement.

The supplement to the Yucca Mountain EIS is available on the NRC’s website at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr2184/.

For additional information, please contact David McIntyre of the NRC at (301) 415-8200.