DRC-2000-001461 - 0901a06880ef6a0d

ML003773008
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555-0001
November 30, 2000
NRC REGULATORY ISSUE SUMMARY 2000-23
RECENT CHANGES TO URANIUM RECOVERY POLICY
ADDRESSEES
All holders of materials licenses for uranium and thorium recovery facilities.
INTENT
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
to inform materials licensees of the Commission’s decisions on four Commission Papers
prepared by the Uranium Recovery staff and the Office of the General Counsel (OGC). All the
policy decisions will be codified in the 10 CFR Part 41 rulemaking that has been initiated. No
specific action nor written response is required.
BACKGROUND
NRC staff prepared four Commission Papers in 1999 to address various uranium recovery
issues. One Commission Paper (SECY-99-011, “Draft Rulemaking Plan; Domestic Licensing of
Uranium and Thorium Recovery facilities - Proposed New 10 CFR Part 41") addressed the
need to revise and update uranium recovery regulations, particularly with respect to in situ leach
(ISL) facilities and recommended the initiation of rulemaking to create a new Part 41 specific to
uranium recovery. The other three Commission Papers addressed issues raised by the
National Mining Association (NMA) in its April 1998 paper, “Recommendations for a
Coordinated Approach to Regulating the Uranium Recovery Industry.” The first of those papers
(SECY-99-012, “Use of Uranium Mill Tailings Impoundments for the Disposal of Other Than
11e(2) Byproduct Materials, and Reviews of Applications to Process Material Other Than
Natural Ore”) discussed the disposal of radioactive waste, other than byproduct material,
defined in section 11e.(2) of the Atomic Energy Act (AEA) of 1954, as amended, in mill tailings
impoundments, and the processing of material, other than natural ore, for source material at
licensed uranium mills. The second of those papers (SECY-99-013, “Recommendations on
ways to Improve the Efficiency of NRC Regulation at In Situ Leach Uranium Recovery
Facilities”) discussed the regulation of ground water at ISL sites and the issue of which waste
streams at ISL facilities come under NRC regulatory jurisdiction as 11e.(2) byproduct material.
The last paper (SECY-99-277, “Concurrent Jurisdiction of Non-Radiological Hazards of
Uranium Mill Tailings”) addressed the issue of concurrent jurisdiction (with States that do not
have Agreement State regulatory authority for 11e.(2) material under section 274 of the AEA)
over the non-radiological hazards of uranium mill tailings.
RIS 2000-23
Page2of7
On July 13, 2000, the Commission issued a Staff Requirements Memorandum (SRM) on
SECY-99-011. On July 26, 2000, the Commission issued SRMs on SECY-99-012 and
SECY-99-013, and on August 11, 2000, the SRM on SECY-99-277 was issued.
The decisions and directions in these SRMs and the staff actions in response are discussed in
sections that follow.
PART 41 RULEMAKING (SECY-99-011)
SECY-99-011 approved the staff’s recommendation to provide a draft Rulemaking Plan (RP) for
comment to the Agreement States, with the preferred option being the creation of a new Part 41
dedicated to uranium recovery regulation. The Commission directed the staff to revise the draft
RP to reflect the Commission’s guidance in the other uranium recovery SRMs.
On September 11, 2000, the staff transmitted the draft RP to all States for comment. The staff
sent the draft RP to all States rather than just Agreement States because the issue of
concurrent jurisdiction regarding non-radiological hazards primarily affects non-Agreement
States, and the staff wanted to give those States an opportunity to comment on the draft RP.
Comments have been received from several States. In addition, the NMA and two licensees
provided comments on the draft RP. The staff will consider all the comments received in
preparing its final RP, which it expects to issue in early 2001.
DISPOSAL OF NON-11e.(2) BYPRODUCT MATERIAL IN TAILINGS IMPOUNDMENTS
(SECY-99-012)
In 1995, the staff published guidance, in the Federal Register (60 FR 49296), for the disposal,
in uranium mill tailings impoundments, of radioactive material that is not byproduct material, as
defined in section 11e.(2) of the AEA. The guidance consisted of 10 criteria to determine
whether to approve a proposed disposal of non-11e.(2) byproduct material in a uranium mill
tailings impoundment. In its 1998 white paper, the NMA emphasized that the criteria were too
restrictive, pointing out that no requests for such disposals have been made since the guidance
was issued. The Commission, in the SRM for SECY-99-012, approved an option that would
allow more flexibility in permitting non-11e.(2) material to be disposed of in tailings
impoundments. The NRC intends to incorporate the criteria into the new Part 41. In the
interim, the Commission directed the staff to implement the SRM.
To comply with the direction in the SRM, the staff is revising the 1995 guidance in the
following manner:
* The staff will remove the prohibitions, found in items 2, 4, and 5, regarding non-AEA
radioactive material and material subject to regulation under other legislative authorities,
such as the Toxic Substance Control Act (TSCA) or the Resource Conservation and
Recovery Act (RCRA).
The staff will add a criterion regarding approval from the appropriate regulators of
TSCA, RCRA, and non-AEA radioactive material for disposal of such material in the
tailings impoundment.
RIS 2000-23
Page3of7
The staff will revise the criterion, in item 8, regarding approval by Low-Level Waste
Compacts, to allow for the situation in which material proposed for disposal does not fall
under the jurisdiction of Low-Level Waste Compacts (e.g., radioactive material not
regulated under the AEA).
The Commission directed the staff to pursue a generic exemption to NRC’s disposal
requirements for low-level radioactive waste in 10 CFR Part 61, rather than having to
grant an exemption, under 10 CFR 61.6, as identified in item 10. A generic exemption
to regulations must be issued through a rulemaking process. Therefore, the staff will
pursue incorporating the generic exemption in the new Part 41. In the interim, the
requirement for a specific exemption will remain in the guidance, with addition of a
caveat for material not regulated under Part 61.
The staff therefore is revising its 1995 guidance. The complete revised guidance, is in
Attachment 1.
PROCESSING OF MATERIAL OTHER THAN NATURAL URANIUM ORES (SECY-99-012)
In 1995, the staff published its position and guidance, in the Federal Register (60 FR 49296),
on the use of uranium feed material other than natural ores (alternate feed material), in uranium
mills. The guidance identified three determinations that the staff had to make in order to
approve an alternate feed request. The third determination -- whether the ore is being
processed primarily for its source material content -- generated considerable controversy. This
determination was required to address the concern that wastes that would otherwise have to be
disposed of as radioactive or mixed waste would be proposed for processing at a uranium mill
primarily to be able to dispose of them in the tailings pile as 11e.(2) byproduct material. This
determination was essentially a determination of the motives of the mill operator in requesting
approval of a specific stream of alternate feed material. In many cases it involved questioning
the financial aspects of acquiring and processing the alternate feed material, and selling the
resultant uranium product.
In its 1998 white paper, the NMA emphasized that NRC should not be looking to a licensee’s
motives in processing alternate feed material. After careful consideration of stakeholder
comments and the staff’s analysis, the Commission, in the SRM for
SECY-99-012, directed the staff to allow processing of alternate feed material without inquiry
into a licencee’s economic motives, and referred to a Commission decision (CLI-00-
01 51 NRC 9) on a specific instance of proposed processing of alternate feed, that was brought
before the Atomic Safety Licensing Board and then appealed to the Commission. The
Commission also addressed the second determination in the 1995 guidance ( i.e., whether the
feed material contains hazardous waste). It directed the staff to allow more flexibility with
regard to this issue consistent with its direction to the staff on the disposal of non-11e.(2)
byproduct material in tailings piles.
The Commission directed the staff to revise, issue, and implement final guidance on the
processing of alternate feed as soon as possible and to codify the guidance in the new Part 41.
To comply with the SRM, the staff is revising the 1995 position and guidance in the
following manner:
RIS 2000-23
Page4of7
The staff will modify the prohibition in item 2 on feed material containing hazardous
waste, to allow such feed material provided that the licensee obtains approval of the
U.S. Environmental Protection Agency (EPA) or the State, and a commitment from the
long-term custodian to accept the tailings after site closure.
The staff will revise the manner in which it determines whether the ore is being
processed primarily for its source material content, to focus on the product of the
processing, and eliminate any inquiry into the licensee’s economic motives for the
processing.
The staff therefore is revising its 1995 guidance. The complete revised guidance, is in
Attachment 2.
CLASSIFICATION OF LIQUID WASTES AT ISL FACILITIES (SECY-99-013)
Before 1995, the staff practice for addressing the disposal of evaporation pond sludges at ISL
facilities relied on a broad reading of the definition of 11e.(2) byproduct material. This broad
reading only addressed discrete surface wastes capable of controlled disposal and did not
distinguish between wastes generated at various phases of an ISL operation. All waste
materials generated during ISL operations and ground-water restoration activities were
designated 11e.(2) byproduct material and disposed of at licensed uranium mill tailings
impoundments, in accordance with 10 CFR Part 40, Appendix A, Criterion 2.
The staff issued two guidance documents in 1995 to address issues raised by the industry in
the uranium recovery program. The first, “Staff Technical Position on Effluent Disposal at
Licensed Uranium Recovery Facilities” (hereinafter, the effluent guidance), was intended to
ensure protection of the environment and public, while providing uranium recovery licensees
with flexibility regarding the disposal of various types of liquid effluents generated during the
operation of their facilities. In issuing this guidance, the staff took a more narrow view of the
definition of 11e.(2) byproduct material. It differentiated between the various waste waters
generated during ISL operations on the basis of their origin and whether uranium was extracted
for its source material content during that phase of the operation. Waste waters and the
associated solids produced during the uranium extraction phase of site operations, called
“production bleed,” were classified as AEA Section 11e.(2) byproduct material and therefore
subject to regulation by NRC. Conversely, waste waters and the resulting solids produced after
uranium extraction (i.e., during ground-water restoration activities) were classified as “mine
waste waters,” and therefore were subject to regulation by individual States under their
applicable mining programs. These wastes were considered naturally occurring radioactive
material (NORM). However, because licensees often dispose of waste waters from uranium
extraction and post-extraction activities in the same evaporation ponds, the resulting solids are
a commingled waste consisting of 11e.(2) byproduct material and sludges derived from mine
waste water.
In the second guidance document, “Final Revised Guidance on Disposal of Non-Atomic Energy
Act of 1954, Section 11e.(2) Byproduct Material in Tailings Impoundments” (hereinafter, the
disposal guidance), the staff identified 10 criteria that licensees should meet before NRC could
authorize the disposal of AEA material other than 11e.(2) byproduct material in tailings
impoundments. One of these criteria prohibited the disposal of radioactive material not covered
by the AEA, including NORM (see earlier discussion for policy revisions). This criterion was
RIS 2000-23
Page5of7
intended to avoid the possibility of dual regulation of the radioactive constituents in the
impoundments, since individual States are responsible for radioactive materials not covered by
the AEA.
The industry expressed concerns, in NMA’s white paper, that, taken together, these two
guidance documents leave no option for the disposal of radioactively contaminated sludges
from ISL evaporation ponds. The reason for this concern is that the 11e.(2) byproduct material
was commingled with a NORM waste, which the disposal guidance prohibits from disposal in a
tailings impoundment. The industry emphasized that the staff’s waste classification, based on
the origin of the waste water (i.e., from the extraction or restoration phase) at an ISL facility,
makes the disposal of such sludges in a mill tailings impoundment, as required under Criterion
2 of 10 CFR Part 40, Appendix A, impossible -- even though the sludges derived from waste
waters produced throughout a facility’s life cycle are physically, chemically, and radiologically
identical.
The staff analyzed several options in SECY-99-013 for addressing the industry’s concerns. In
the SRM for SECY-99-013, the Commission determined that all liquid effluents at ISL uranium
recovery facilities are 11e.(2) byproduct material. NRC takes the position that any waste water
generated during or after the uranium extraction phase of site operations, and all evaporation
pond sludges derived from such waste waters, are classified as 11e.(2) byproduct material.
The staff will make no legal distinction among the waste waters produced at different stages in
a facility’s life cycle.
This revised policy is effective immediately. The staff intends to codify this policy in the new
rulemaking for Part 41 and associated regulatory guidance.
GROUND-WATER ISSUES AT ISL FACILITIES (SECY-99-013)
Over the past several years, the industry has expressed concern that NRC’s regulation of
ground water at ISLs is duplicative of the ground-water protection programs required by the
Safe Drinking Water Act (SDWA), as administered by EPA or EPA-authorized States. EPA and
the States protect ground-water quality through the Underground Injection Control (UIC)
program, under the SDWA. The States often require additional measures in the UIC program
that are more stringent than the Federal program. As presented in NMA’s white paper, the
industry contended that NRC’s review and licensing activities are a duplicative form of
regulation covering the same issues. Additionally, NMA also expressed the view that NRC did
not have authority to regulate ground water at ISLs.
Historically, NRC has imposed conditions on ISL operations to ensure that ground-water quality
is maintained during licensed activities and that actions are taken to ensure the restoration of
ground-water quality before the license is terminated. The specific conditions imposed in an
ISL license have typically been the result of NRC’s independent review, as documented in
safety evaluation reports and appropriate environmental evaluations.
In addition to NRC’s review, licensees must also obtain a UIC permit from EPA or the EPA-
authorized State before uranium recovery operations can begin. EPA or the authorized State
conducts many of the same types of reviews as NRC. This is evidenced by NRC incorporating
ground-water protection limits from a State’s permitting program into specific license
RIS 2000-23
Page6of7
requirements, after conducting its own review of the licensee’s groundwater protection program,
including the use of State-imposed standards -- and staff routinely accepting specific
methodologies and guidance developed by EPA or States for ground-water monitoring
programs and well construction.
In the SRM for SECY-99-013, the Commission approved the staff continuing discussions with
EPA and appropriate States to determine the extent to which NRC can rely on the EPA UIC
program for ground-water protection issues, thereby potentially minimizing duplicative review of
ground-water protection at ISL facilities. Part of the discussions with EPA and appropriate
States should include appropriate methods to implement any agreements, including
Memoranda of Understanding (if necessary) and potential requirements that could be
incorporated in the new Part 41. In the interim, it is recognized that some NRC/EPA dual
regulation of the ground-water at ISL facilities will continue until such time that NRC can defer
to EPA's UIC program.
NRC has initiated a new round of discussions with the EPA since the Commission decision in
July 2000, and discussions with the appropriate States should begin in early to mid 2001.
In February 1998, staff documented its review process for ISLs, including a detailed evaluation
of ground-water activities, in a draft Standard Review Plan (draft SRP) for ISL facility license
applications (NUREG-1569), that was published for public comment. Following the comment
period, staff held a public workshop on the SRP to discuss the issues raised. The staff intends
to use the draft SRP in licensing reviews until the rulemaking for new Part 41 (SECY 99-011)
has been completed and NUREG-1569 is finalized.
CONCURRENT JURISDICTION OF NON-RADIOLOGICAL HAZARDS OF URANIUM MILL
TAILINGS (SECY-99-277)
In 1980, the staff considered the issue of whether the Uranium Mill Tailings Radiation Control
Act (UMTRCA) preempts a non-Agreement State’s authority to regulate the non-radiological
hazards associated with 11e.(2) byproduct material and concluded that it did not. The NRC
concluded that NRC and the State both exercised this authority. As a result, the staff has
followed the practice of sharing jurisdiction of the non-radiological hazards with States. In its
1998 white paper, the NMA questioned the 1980 staff interpretation of UMTRCA. The
Commission, in the SRM for SECY-99-0277 determined that NRC has exclusive jurisdiction
over both the radiological and non-radiological hazards of 11e.(2) byproduct material.
As a result of this decision, the staff will implement its exclusive authority over the non-
radiological hazards of 11e.(2) byproduct material and not recognize State authority in this area.
SUMMARY OF ISSUES
The Commission has evaluated a range of uranium recovery issues and the staff evaluation
and has directed, through SRMs, the staff to take various actions that will ultimately be
incorporated into the new Part 41 rulemaking and existing uranium recovery SRPs.
RIS 2000-23
Page7of7
In the interim, this RIS informs the licensees of the Commission’s decisions. These are: 1) to
allow more flexibility in the disposal of non-11e.(2) material in tailings impoundments, subject to
certain considerations; 2) to allow alternate feed material to be processed for uranium (or
thorium) without any inquiry into a licensee’s economic motives; 3) to classify all waste water
and sludges generated during or after the uranium (or thorium) extraction phase of in situ leach
operations as 11e.(2) byproduct material; 4) to continue discussions with EPA and appropriate
States to determine the extent that NRC can rely on the EPA UIC program for ground-water
protection at ISL facilities; and 5) to note that NRC has exclusive jurisdiction over both the
radiological and non-radiological hazards of 11e.(2) byproduct material.
This regulatory issue summary requires no specific action nor written response. If you have
any questions about this summary, please contact the technical contact listed below.
/RA/
Michael F. Weber, Director
Division of Fuel Cycle Safety & Safeguards
Office of Nuclear Material Safety and
Safeguards
Technical Contact: Kenneth R. Hooks, NMSS
301-415-7777
E-mail: [e-mail]
Attachments:
1. Interim Guidance Non-11e.(2)
2. Interim Position Alternate Feed
3. List of Recently Issued NRC Regulatory Issue Summaries
RIS 2000-23
Page7of7
In the interim, this RIS informs the licensees of the Commission’s decisions. These are: 1) to
allow more flexibility in the disposal of non-11e.(2) material in tailings impoundments, subject to
certain considerations; 2) to allow alternate feed material to be processed for uranium (or
thorium) without any inquiry into a licensee’s economic motives; 3) to classify all waste water
and sludges generated during or after the uranium (or thorium) extraction phase of in situ leach
operations as 11e.(2) byproduct material; 4) to continue discussions with EPA and appropriate
States to determine the extent that NRC can rely on the EPA UIC program for ground-water
protection at ISL facilities; and 5) to note that NRC has exclusive jurisdiction over both the
radiological and non-radiological hazards of 11e.(2) byproduct material.
This regulatory issue summary requires no specific action nor written response. If you have
any questions about this summary, please contact the technical contact listed below.
/RA/
Michael F. Weber, Director
Division of Fuel Cycle Safety & Safeguards
Office of Nuclear Material Safety and
Safeguards
Technical Contact: Kenneth R. Hooks, NMSS
301-415-7777
E-mail: [e-mail]
Attachments:
1. Interim Guidance Non-11e.(2)
2. Interim Position Alternate Feed
3. List of Recently Issued NRC Regulatory Issue Summaries
WITS 200000028/NMSS200000512
DISTRIBUTION: Public FCSS r/f NMSS r/f FCLB r/f MMoraity
JDelgado CPoland MBridgers EDO r/f
DOCUMENT PATH AND FILE NAME:C:\RIS ISL Issues WITS200000028.wpd
OFC FCSS FCSS FCSS TED ACNW MSIB FCSS
NAME KHooks DGillen PTing EKraus (via fax) N/A KRamsey (via HC) MWeber
DATE 11/27/00 11/30/00 11/30/00 11/27/00 11/17/00 11/30/00
Attachment 1
RIS 2000-23
Page1of2
Interim Guidance on Disposal of Non-Atomic Energy Act of 1954, Section 11e.(2)
Byproduct Material in Tailings Impoundments
1. In reviewing licensee requests for the disposal of wastes that have radiological
characteristics comparable to those of Atomic Energy Act of 1954, Section 11e.(2)
byproduct material [hereafter designated as "11e.(2) byproduct material"] in tailings
impoundments, the Nuclear Regulatory Commission staff will follow the guidance set
forth below. Since mill tailings impoundments are already regulated under
10 CFR Part 40, licensing of the receipt and disposal of such material [hereafter
designated as "non-11e.(2) byproduct material"] should also be done under
10 CFR Part 40.
2. Special nuclear material and Section 11e.(1) byproduct material waste should not be
considered as candidates for disposal in a tailings impoundment, without compelling
reasons to the contrary. If staff believes that such material should be disposed of in a
tailings impoundment in a specific instance, a request for Commission approval should
be prepared.
3. The 11e.(2) licensee must provide documentation showing necessary approvals of
other affected regulators (e.g., the U.S. Environmental Protection Agency or State) for
material containing listed hazardous wastes or any other material regulated by another
Federal agency or State because of environmental or
safety considerations.
4. The 11e.(2) licensee must demonstrate that there will be no significant environmental
impact from disposing of this material.
5. The 11e.(2) licensee must demonstrate that the proposed disposal will not
compromise the reclamation of the tailings impoundment by demonstrating compliance
with the reclamation and closure criteria of Appendix A of 10 CFR Part 40.
6. The 11e.(2) licensee must provide documentation showing approval by the Regional
Low-Level Waste Compact in whose jurisdiction the waste originates as well as approval
by the Compact in whose jurisdiction the disposal site is located, for material which
otherwise would fall under Compact jurisdiction.
7. The U.S. Department of Energy (DOE) and the State in which the tailings
impoundment is located, should be informed of the U.S. Nuclear Regulatory
Commission findings and proposed action, with a request to concur within 120 days. A
concurrence and commitment from either DOE or the State to take title to the tailings
impoundment after closure must be received before granting the license amendment to
the 11e.(2) licensee.
Attachment 1
RIS 2000-23
Page2of2
8. The mechanism to authorize the disposal of non-11e.(2) byproduct material in a
tailings impoundment is an amendment to the mill license under 10 CFR Part 40,
authorizing the receipt of the material and its disposal. Additionally, an exemption to the
requirements of 10 CFR Part 61, under the authority of 10 CFR 61.6, must be granted, if
the material would otherwise be regulated under Part 61. (If the tailings impoundment is
located in an Agreement State with low-level waste licensing authority, the State must
take appropriate action to exempt the non-11e.(2) byproduct material from regulation as
low-level waste.) The license amendment and the 10 CFR 61.6 exemption should be
supported with a staff analysis addressing the issues discussed in this guidance.
Attachment 2
RIS 2000-23
Page1of2
Interim Position and Guidance on the Use of Uranium Mill Feed Material Other
Than Natural Ores
In reviewing licensee requests to process alternate feed material (material other than
natural ore) in uranium mills, the Nuclear Reguatory Commission staff will follow the
guidance presented below. Besides reviewing to determine compliance with appropriate
aspects of Appendix A of 10 CFR Part 40, the staff should also address the following
issues:
1. Determination of whether the feed material is ore.
For the tailings and wastes from the proposed processing to qualify as 11e.(2)
byproduct material, the feed material must qualify as "ore." In determining whether the
feed material is ore, the following definition of ore will be used:
Ore is a natural or native matter that may be mined and treated for the extraction of any
of its constituents or any other matter from which source material is extracted in a
licensed uranium or thorium mill.
2. Determination of whether the feed material contains hazardous waste.
If the proposed feed material contains hazardous waste, listed under subpart D Sections
261.30-33 of 40 CFR (or comparable Resource Conservation and Recovery Act (RCRA)
authorized State regulations), it would be subject to the U.S. Environmental Protection
Agency (EPA) or State regulation under RCRA. If the licensee can show that the
proposed feed material does not contain a listed hazardous waste, this issue is
resolved.
Feed material exhibiting only a characteristic of hazardous waste (ignitable, corrosive,
reactive, toxic) would not be regulated as hazardous waste and could therefore be
approved for recycling and extraction of source material. However, this does not apply
to residues from water treatment, so determination that such residues are not subject to
regulation under RCRA will depend on their not containing any characteristic hazardous
waste. Staff may consult with EPA (or the State) before making a determination of
whether the feed material contains hazardous waste.
If the feed material contains hazardous waste, the licensee can process it only if it
obtains EPA (or State) approval and provides the necessary documentation to that
effect. Additionally, for feed material containing hazardous waste, the staff will review
documentation from the licensee that provides a commitment from the U.S. Department
of Energy or the State to take title to the tailings impoundment after closure.
Attachment 2
RIS 2000-23
Page2of2
3. Determination of whether the ore is being processed primarily for its source-
material content.
For the tailings and waste from the proposed processing to qualify as 11e.(2) byproduct
material, the ore must be processed primarily for its source-material content. If the only
product produced in the processing of the alternate feed is uranium product, this
determination is satisfied. If, in addition to uranium product, another material is also
produced in the processing of the ore, the licensee must provide documentation
showing that the uranium product is the primary product produced.
If it can be determined, using the aforementioned guidance, that the proposed feed
material meets the definition of ore, that it will not introduce a hazardous waste not
otherwise exempted, or if it has been approved by the EPA (or State) and the long-term
custodian, and that the primary purpose of its processing is for its source-material
content, the request can be approved.
______________________________________________________________________________________
OL = Operating License
CP = Construction Permit
Attachment 3
RIS 2000-23
Page1of1
LIST OF RECENTLY ISSUED
NRC REGULATORY ISSUE SUMMARIES
_____________________________________________________________________________________
Regulatory Issue Date of
Summary No. Subject Issuance Issued to_____________________________________________________________________________________
2000-22 Issues Stemming from NRC Staff
Review of Recent Difficulties
Experienced in Maintaining Steam
Generator Tube Integrity
11/03/00 All holders of Ols for pressurized-
water reactors (PWRs), except
those who have permanently
ceased operations and have
certified that fuel have been
permanently removed from the
reactor vessel
2000-21 Changes to the Unplanned Scram
and Unplanned Scram With Loss
of Normal Heat Removal
Performance Indicators
10/31/00 All holders of OLs for nuclear
power reactors, except those who
have permanently ceased
operations and have certified that
fuel has been permanently
removed from the reactor vessel
2000-20 Advance Notice of Intent to Pursue
License Renewal
11/14/2000 All holders of OLs for nuclear
power reactors, except those
licensees who have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor vessel
2000-19 Partial Release of Reactor Site for
Unrestricted Use Before NRC
Approval of the License
Termination Plan
10/24/00 All holders of OLs for nuclear
power reactors, including those
licensees who have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor vessel