In the Matter of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; Director's Decision, 14997-15001 [2011-6401]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 76, Number 53 (Friday, March 18, 2011)]
[Notices]
[Pages 14997-15001]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-6401]


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NUCLEAR REGULATORY COMMISSION

[NRC-2011-0060; Docket No. 50-271; License No. DPR-28]


In the Matter of Entergy Nuclear Vermont Yankee, LLC and Entergy 
Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station; 
Director's Decision

I. Introduction

    By letters dated January 12, 2010, from Mr. Michael Mulligan, 
February 8, 2010, from Mr. Raymond Shadis, and February 20, 2010, from 
Mr. Thomas Saporito, these individuals (collectively ``Petitioners'') 
filed separate petitions pursuant to Title 10 of the Code of Federal 
Regulations (10 CFR), Section 2.206, requesting the Nuclear Regulatory 
Commission (NRC or the Commission) take actions with regard to the 
Vermont Yankee Nuclear Power Station (VY).
    Mr. Mulligan requested in his petition that: (1) The radioactive 
leak into the environment of VY be immediately stopped, VY be 
immediately shut down, and all leaking paths be isolated; and (2) VY 
disclose its preliminary ``root cause analysis,'' and the NRC release 
its preliminary investigative report on that analysis before plant 
startup.
    Mr. Shadis on behalf of New England Coalition (NEC) requested in 
his petition that the NRC: (1) Require VY to go into cold shutdown and 
depressurize all systems in order to slow or stop the leak; (2) act 
promptly to stop or mitigate the leak(s); (3) require VY to reestablish 
its licensing basis by physically tracing records and reporting 
physical details of all plant systems that would be within scope as 
``Buried Pipes and Tanks,'' in NUREG-1801, ``Generic Aging Lessons 
Learned (GALL) Report,'' and under the requirements of 10 CFR 50.54, 
``Conditions of licenses''; (4) investigate and determine why Entergy 
has been allowed to operate VY since 2002 without a working knowledge 
of all plant systems and why the NRC's Reactor Oversight Process (ROP) 
and review process for license renewal amendment did not detect this 
dereliction; (5) take notice of VY's many maintenance and management 
failures (from 2000-2010) and the ROP's failure to detect them early 
and undertake a full diagnostic evaluation team inspection using NRC 
Inspection Procedure 95003, ``Supplemental Inspection for Repetitive 
Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow 
Inputs or One Red Input''; and (6) require VY to apply for an amendment 
to its license renewal application that would address both aging 
analysis and aging management of all buried piping carrying or with the 
potential to carry radionuclides and/or the potential to interact with 
any safety or safety-related system.
    Mr. Saporito requested in his petition that the NRC: (1) Order a 
cold shutdown mode of operation for VY because of leaking radioactive 
tritium; and (2) issue a confirmatory order modifying the NRC-issued 
license for VY so that the licensee must bring the nuclear reactor to a 
cold shutdown mode of operation until the licensee can provide 
definitive reasonable assurance to the NRC, under affirmation, that the 
reactor will be operated in full compliance with the regulations in 10 
CFR Part 50, ``Domestic Licensing of Production and Utilization 
Facilities,'' and Appendix A, ``General Design Criteria for Nuclear 
Power Plants,'' to 10 CFR Part 50, Criterion 60, ``Control of Releases 
of Radioactive Materials to the Environment,'' and Criterion 64, 
``Monitoring Radioactivity Releases,'' and other NRC regulations and 
authority.
    Mr. Shadis stated during a public teleconference with the PRB on 
March 3, 2010, that the tritium leak is just one example of many 
maintenance and management failures at VY. All three petitioners raised 
a concern regarding what they perceive as the NRC's failure to examine 
the deficiencies at VY in an integrated manner. This concern has met 
the criteria for review in accordance with NRC's Management Directive 
(MD) 8.11 ``Review Process for 10 CFR 2.206 Petitions.''
    In an acknowledgment letter dated June 25, 2010, the petitioners 
were informed of the PRB's decision to deny the request for an 
immediate cold shutdown of VY because the PRB did not identify any 
urgent safety concerns. The NRC also informed the petitioners that 
their petitions were consolidated per the guidance in MD 8.11. The 
consolidated petition was accepted for review for the following 
specific issues and concerns stated by the petitioners in the petitions 
and/or supplemented during the teleconferences:
    (1) Increasing concentrations of radiocontaminants in the soil and 
groundwater at VY, as well as an increasing area of contamination, are 
manifest on a daily basis. VY risks aggravating the contamination by 
continuing to run the reactor at full power while attempting over a 
period of a month to triangulate the location of a presumed leak by 
drilling a series of test wells in the affected area.
    (2) During the license renewal application proceeding, the licensee 
averred that it was unaware of the existence of some buried pipes, now 
uncovered, and it has yet to discover their path and purpose.
    (3) Entergy has, in 8 years of ownership, failed to learn and 
understand VY's design, layout, and construction. This failure to 
comprehend and understand the layout, function, and potentially the 
interaction of the plant's own piping systems constitutes a loss of 
design basis.
    (4) The NRC's ROP has apparently failed to capture, anticipate, and 
prevent ongoing maintenance, engineering, quality assurance, and 
operation issues that have manifested themselves in a series of high-
profile incidents since Entergy took over VY. The agency has repeatedly 
failed to detect root cause trends until they have, as in this 
instance, become grossly self-revealing.
    (5) The NRC should ensure that Entergy has adequate decommissioning 
funds. The tritium leak will increase decommissioning costs because of 
the need for site radiological examination and soil remediation.
    Copies of the petitions are available for inspection at the 
Commission's Public Document Room (PDR) at One White Flint North, Room 
O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852, 
and from the NRC's Agencywide Documents Access and Management System 
(ADAMS) Public Electronic Reading Room on the NRC Web site at https://www.nrc.gov/reading-rm/adams.html under ADAMS Accession Nos. 
ML100190688, ML100470430, and ML100621374. Refer to NRC's Management 
Directive 8.11, ``Review Process for 10 CFR 2.206 Petitions,'' (ADAMS 
Accession No. ML041770328), for a description of the petition review 
process. Persons who do not have access to ADAMS or who have problems 
in accessing the documents in ADAMS should contact the NRC PDR 
reference staff by telephone at 1-800-397-4209 or 301-415-4737, or by 
e-mail to pdr.resource@nrc.gov.

II. Discussion

    On January 7, 2010, Entergy reported to the NRC that water samples 
taken from groundwater monitoring well GZ-3 onsite at VY showed tritium 
levels above background. GZ-3 is about 70 feet from the Connecticut 
River. Tritium is another name for the radioactive nuclide hydrogen-3. 
Tritium occurs naturally in the environment because of cosmic ray 
interactions. It is also

[[Page 14998]]

produced by nuclear reactor operations, and can be legally discharged 
as a radioactive effluent under NRC regulations. Tritium is chemically 
identical to normal hydrogen (hydrogen-1), and, like normal hydrogen, 
tends to combine with oxygen to form water, which is referred to as 
tritiated water. The detection of tritiated water in the monitoring 
well indicated abnormal leakage from the nuclear plant. The 
Environmental Protection Agency's (EPA's) regulatory standard for 
tritium in drinking water is 20,000 picocuries per liter (pCi/L). 
Tritium was initially measured at levels up to about 17,000 pCi/L in 
monitoring well GZ-3, which is not used for drinking water. Samples at 
other monitoring wells have also shown some tritium. The highest 
reading from any monitoring well has been about 2.5 million pCi/L, from 
monitoring well GZ-10. Entergy immediately started an investigation to 
identify the source of the tritium, and later installed additional 
monitoring wells to help locate the source.
    Upon notification on January 7, 2010, of the detection of tritium 
in the monitoring well, the NRC's staff initiated actions to review and 
assess the condition, by reviewing all available sampling data, 
hydrologic information, and analyses; conducting an onsite inspection 
and assessment of Entergy's plans and process for investigating the 
condition; and making an independent determination of public health and 
safety consequence based on available information. NRC inspectors 
provided close regulatory oversight of Entergy's investigation in order 
to independently assure conformance with applicable NRC regulatory 
requirements, assess licensee performance, and evaluate the condition 
with respect to NRC's radiological release limits.
    On February 27, 2010, following excavation and leak testing of the 
Advanced Off Gas (AOG) system pipe tunnel, Entergy reported that it had 
identified leakage into the surrounding soil, and therefore to the 
groundwater, from an unsealed joint in the concrete tunnel wall. The 
AOG pipe tunnel is located about 15 feet underground. Also, piping 
inside the tunnel had previously been found to be leaking, and the 
drain inside the tunnel had been found to be clogged. Soil samples in 
the vicinity showed traces of radioactive isotopes. Entergy reported 
that the leakage to the environment had been stopped by isolating 
piping and containing the water leaking from the AOG pipe tunnel. 
However, on May 28, 2010, Entergy reported a second leak from AOG 
piping into the soil. Entergy quickly isolated this leak and has sealed 
off that piping to prevent further leaks in that area. The contaminated 
soil was removed from the excavated area and is being stored in 
containers onsite for eventual disposal in accordance with NRC 
regulatory requirements.
    As part of its oversight effort, NRC staff conducted an evaluation 
in accordance with NRC Manual Chapter 0309, ``Reactive Inspection 
Decision Basis for Reactors,'' from January 25 to April 10, 2010, to 
determine if the occurrence with the AOG piping constituted a 
significant operational event (i.e., a radiological, safeguards, or 
other safety-related operational condition) that posed an actual or 
potential hazard to public health and safety, property, or the 
environment. The evaluation reviewed the condition against the 
specified deterministic criteria that are based on regulatory safety 
limits, and determined that none of the criteria were met. 
Notwithstanding that determination, the NRC staff continued its review, 
oversight, and assessment of the condition, including an independent 
evaluation of any potential public health and safety consequences. The 
staff's activities included:
    1. Several onsite inspections and reviews to assess radiological 
and hydrological data to establish reasonable assurance that members of 
the public were not, nor were they expected to be, exposed to radiation 
in excess of the dose limits for individual members of the public 
specified in 10 CFR 20.1301, (i.e., 100 millirem in a year) or the As 
Low As Is Reasonably Achievable (ALARA) dose objectives specified in 10 
CFR Part 50, Appendix I.
    2. Engagement of hydrological scientists from NRC's Office of 
Nuclear Reactor Regulation, Office of Regulatory Research, and the U.S. 
Geological Survey to independently assess the licensee's hydrological 
and geological data and conclusions on groundwater flow characteristics 
of the area.
    3. Inspection in accordance with NRC Temporary Instruction TI-2515/
173, ``Review of the Implementation of the Industry Ground Water 
Protection Voluntary Initiative,'' to determine the licensee's 
implementation of the specifications in the industry's groundwater 
initiative document NEI-07-07, ``Industry Ground Water Protection 
Initiative--Final Guidance Document,'' (ADAMS Accession No. 
ML072610036).
    4. Confirmation of the basis, calculational methodology, and 
results obtained by the licensee to estimate a contaminated groundwater 
effluent release and off-site dose consequence to members of the 
public.
    5. Analysis of selected ground water and environmental samples to 
aid in determining the adequacy of the licensee's analytical methods.
    6. Approval for additional NRC inspection resources above the 
baseline inspection program to fully evaluate and provide continuing 
regulatory oversight of the licensee's investigation and remediation 
activities.
    7. Documentation of the inspection scope and conclusions in 
publicly available NRC Inspection Reports.
    As a result of these activities, the NRC established reasonable 
assurance, in a timely manner, that this groundwater condition would 
not result in any dose consequence that would jeopardize public health 
and safety. To date, information and data continue to support that the 
dose consequence attributable to the groundwater condition at VY 
remains well below the ``As Low As Reasonably Achievable'' (ALARA) dose 
objectives specified in 10 CFR Part 50, Appendix I; and that the NRC 
regulatory criteria of 10 CFR 20.1301, ``Dose limits for individual 
members of the public,'' was never approached.
    In addition, representatives from the State of Vermont observed NRC 
inspection activities and conducted independent analyses of collected 
groundwater samples.
    As discussed in Section I, the specific concerns raised by the 
petitioners which are used as the basis for their requests are 
discussed in the following paragraphs.

A. NRC Response to the Consolidated Petition

1. Concern 1--Increasing Concentrations of Radiocontaminants in the 
Soil and Groundwater at VY
    In order to address/remove the onsite contamination, Entergy 
installed an extraction well (GZ-EW1) on March 23, 2010. On April 7, 
2010, Entergy placed into service a second extraction well (GZ-EW1A), 
with a higher flow capacity. As the plume progressed toward the 
Connecticut River, the extraction wells were sited accordingly, with 
GZ-15 being utilized for groundwater extraction at various times 
starting on July 28, 2010, followed by installation of extraction well 
EW-2 which began operation along with GZ-14 on September 13, 2010. As 
of December 21, 2010, Entergy has pumped approximately 307,000 gallons 
of groundwater out of these wells in order to reduce the amount of 
tritiated water in the groundwater. About 9,000 gallons of the 
extracted water was recycled to the facility, and about

[[Page 14999]]

298,000 gallons of the extracted water has been shipped off-site for 
processing. Data indicates that the remaining residual plume of 
tritiated groundwater is currently migrating from the source of the 
leak to the Connecticut River, which is the direction of flow for the 
groundwater in this location. Notwithstanding the hydrology, no 
detectable tritium has been found in the Connecticut River. The NRC's 
inspections to date confirm that no Federal regulatory limits have been 
exceeded, and public health and safety remain unaffected.
    The soil in the vicinity of the leak was contaminated with small 
amounts of radioactive particulates associated with nuclear plant 
operations, including manganese-54, cobalt-60, zinc-65, strontium-90, 
and cesium-137. Sampling indicated very little migration in the 
immediate area, which is typical for these radionuclides. Entergy has 
removed about 150 cubic feet of contaminated soil and packaged it for 
eventual disposal in accordance with NRC regulatory requirements. 
Although some minor amounts of contaminated soil may remain, NRC 
inspections indicate that this soil poses no threat to public health 
and safety. Areas of remaining minor contamination are expected to be 
evaluated, and as appropriate, remediated during plant decommissioning. 
The NRC's experience with decommissioned nuclear plants such as Maine 
Yankee, Haddam Neck, and Yankee Rowe indicates that these areas can be 
successfully remediated during decommissioning. The NRC's inspections 
indicate that no Federal regulatory limits have been exceeded, and 
there are no health or safety concerns for members of the public or 
plant workers. The initial NRC inspection covered the period of January 
25 through April 14, 2010. Inspection results were initially discussed 
in an NRC inspection report with preliminary results, dated April 16, 
2010 (ADAMS Accession No. ML101060419). The NRC issued its completed 
report on May 20, 2010 (ADAMS Accession No. ML101400040), and continued 
to inspect the licensee's actions in these areas. The follow-up NRC 
Inspection Report 05000271/2010010 was issued on January 7, 2011, ADAMS 
Accession No. ML110070085.
    As part of its corrective action program, Entergy performed a root 
cause analysis (RCA) of the leakage event. The NRC assessed the 
comprehensiveness of this analysis and documented this review in NRC 
Inspection Report 05000271/2010009 dated October 13, 2010 (ADAMS 
Accession No. ML102860037). The NRC concluded that Entergy's root and 
apparent cause evaluations for the tritium ground water leakage events 
were appropriate and no violation of NRC requirements was identified.
    As discussed, Entergy has identified the source of the leak and 
stopped it, and has reduced the onsite contamination by pumping out 
contaminated groundwater and removing about 150 cubic feet of 
contaminated soil. The NRC's inspections confirm that no Federal 
regulatory limits have been exceeded, and the public health and safety 
remains unaffected. Thus, no enforcement action is warranted for this 
concern.
2. Concern 2--VY Was Unaware of the Existence of Some Buried Pipes 
During License Renewal Application Proceeding
    On February 24, 2010, Entergy informed the NRC that some employees 
at VY had been removed from their site positions and placed on 
administrative leave. Entergy took these actions as a result of 
Entergy's independent internal investigation into alleged contradictory 
or misleading information provided to the State of Vermont that was not 
corrected. On May 27, 2010, an NRC audit team completed an onsite audit 
to independently verify that information provided by Entergy material 
to the renewal of the VY operating license was complete and accurate. 
The NRC staff reviewed the VY yard piping drawings to independently 
identify buried and underground piping located onsite. The NRC staff 
performed walk-downs of yard areas and conducted interviews with the 
buried piping program engineer. The NRC staff also reviewed the results 
of system walk-downs previously performed by NRC inspectors during the 
performance of NRC Inspection Procedure (IP) 71002, ``License Renewal 
Inspection,'' as documented in NRC Inspection Report 05000271/2007006, 
dated June 4, 2007 (ADAMS Accession No. ML071550330). Additionally, the 
NRC staff had the opportunity to observe exposed portions of buried 
piping that had been previously excavated by Entergy in conjunction 
with actions taken to investigate the cause of a leak from an 
underground portion of piping in the AOG system. The NRC staff compared 
the results of this review to a list of buried and underground piping 
Entergy had provided in preparation of the audit. The NRC staff did not 
find any discrepancies between Entergy's current accounting of buried 
and underground safety-related piping and the description contained in 
the license renewal application, and so concluded that all information 
provided to the NRC in the license renewal application was complete and 
accurate in accordance with 10 CFR 50.9. Note that non-safety 
underground piping is excluded from the license renewal process. The 
complete audit report dated September 3, 2010, may be found under ADAMS 
Accession No. ML102070412. Because the NRC staff did not identify a 
violation of NRC requirements, no enforcement action is warranted for 
this concern.
3. Concern 3--Entergy's Failure To Comprehend and Understand the 
Layout, Function, and Potentially the Interaction of the Plant's Own 
Piping Systems Constitutes a Loss of Design Basis
    The design basis for VY is the information that ``identifies the 
specific functions to be performed by a structure, system or component 
of a facility, and the specific values or ranges of values chosen for 
controlling parameters as reference bounds for design.'' The design 
basis is submitted to the NRC and is approved by the NRC by issuance of 
the facility operating license. Any changes to the facility as 
described in the final safety analysis report (FSAR) must be either 
submitted to the NRC for approval through a license amendment, or 
changed in accordance with the provisions of 10 CFR 50.59. Licensees 
are required under 10 CFR 50.71(e) to update the FSAR, which was 
originally submitted as part of the application for the license, to 
assure that the information included in the FSAR contains the latest 
information developed. These submittals contain all the changes 
necessary to reflect information and analyses submitted to the 
Commission since the last update to the FSAR. The submittal includes 
the effects of all changes made in the facility or procedures as 
described in the FSAR and all safety analyses and evaluations performed 
by the licensee in support of approved license amendments or in support 
of conclusions that the plant design change did not require a license 
amendment.
    As discussed in previous Section A.2, an NRC audit team compared 
the information Entergy provided in the license renewal application to 
the VY Technical Specifications and the FSAR. The NRC staff determined 
that the information in the FSAR would meet the requirements of 10 CFR 
50.71(e) regarding maintenance of design basis information, consistent 
with the definition of ``design bases'' in 10 CFR

[[Page 15000]]

50.2, and reflects current plant design. Both safety and non-safety 
underground yard piping are depicted on drawings in the VY's controlled 
drawings system. The staff concluded that the information reviewed was 
accurate and complete and the NRC staff did not identify any loss of 
the design basis. Because no violations of NRC requirements were 
identified, enforcement action is not warranted for this concern.
4. Concern 4--The NRC's ROP Failure To Detect Root Cause Trends of a 
Series of High-Profile Incidents
    While a failure of the NRC's ROP is not something for which the NRC 
could take enforcement action against VY, the NRC staff is responding 
to the petitioners' concern. Objectives of the ROP include: (1) 
Improving the objectivity of reactor oversight so that subjective 
decisions and judgment are not central process features; (2) improving 
the scrutability of reactor oversight so that NRC actions have a clear 
tie to licensee performance; and (3) risk-informing reactor oversight 
so that NRC and licensee resources are focused on those aspects of 
performance having the greatest impact on safe plant operation.
    The ROP evaluates plant performance using objective, risk-informed 
thresholds, which include the safety significance of inspection 
findings and performance indicators (PIs). Objective performance 
thresholds are intended to help determine the level of regulatory 
engagement appropriate to licensee performance in each cornerstone 
area. The thresholds were established so that sufficient margin existed 
between nominal performance bands to allow for licensee initiatives to 
correct performance problems before they warrant escalated regulatory 
involvement. Sufficient margin exists to allow for both NRC and 
licensee corrective actions to be taken in response to declining 
performance before plant operation becomes unsafe. Under the ROP, 
performance deficiencies that have no impact on safety are considered 
minor and are entered into a licensee's corrective action program for 
appropriate attention, but they do not result in any specific action by 
the NRC. However, the NRC reviews the licensee's corrective action 
program on a routine basis while performing the baseline inspection 
program, and the staff performs more in-depth reviews on a periodic 
basis while performing the inspection procedure, ``Problem 
Identification and Resolution.''
    In addition to continuous inspection and assessment of VY 
performance, annual and mid-cycle assessments of VY performance are 
conducted. Annual and mid-cycle assessments involve review of the 
safety significance and common factors associated with inspection 
findings, and review of licensee objective performance indicators. The 
results associated with the last several reviews indicate that VY is 
being operated in a manner which preserves public health and safety. 
The high profile events referenced by the petitioners were inspected by 
a combination of specialist inspectors from both the NRC regional 
office and NRC headquarters, and by the onsite resident inspector 
staff. These events were determined to either not involve systems 
important to plant safety, or involved performance deficiencies of very 
low safety significance. In June 2009, the NRC conducted a Problem 
Identification and Resolution inspection at VY. The results of this 
inspection indicated that VY was generally effective in the 
implementation of its corrective action program; additionally, the 
safety culture of station employees, including station management, 
indicated that personnel had a willingness to identify, evaluate, and 
resolve plant deficiencies. The current and past performance 
information, including the Mid-Cycle and Annual Assessment Letters and 
inspection reports issued to VY and other licensees, are publically 
available and presented on the NRC's public Web site.
    The ROP Action Matrix is used to determine the level of regulatory 
oversight warranted for varying levels of performance. VY is in Column 
1 (Licensee Response Column) of the ROP Action Matrix because all 
inspection findings and PIs at this site have very low (i.e., green) 
safety significance. In accordance with Inspection Manual Chapter (IMC) 
0305, ``Operating Reactor Assessment Program,'' plants in Column 1 meet 
all cornerstone objectives and receive the NRC's baseline inspection 
program.
    The deviation process described in IMC 0305 is used to address 
unique situations where the oversight defined by the ROP Action Matrix 
column might not be appropriate or sufficient. Even though performance 
at VY had not crossed any thresholds warranting additional regulatory 
oversight, the staff considered it appropriate to apply additional 
resources to monitor the licensee's efforts to address the onsite 
groundwater contamination and to follow up on the licensee's response 
to the NRC's Demand for Information dated March 1, 2010 (ADAMS 
Accession No. ML100570237). The staff requested and received 
authorization from the NRC's Executive Director for Operations (EDO) on 
April 5, 2010 (ADAMS Accession No. ML100960321), to deviate from the 
ROP Action Matrix to apply additional resources in these areas of 
licensee performance.
    Although tritium has been found in onsite monitoring wells, the 
staff has not identified a hazard to public health and safety, and the 
staff expects any off-site radiological releases to be very small 
(i.e., off-site doses, if any, would be negligible with respect to 
those received from normal background radiation levels). Nevertheless, 
as noted in the Action Matrix deviation memorandum, increased NRC 
oversight of the characterization, mitigation, and remediation of the 
tritium contamination was warranted given the extraordinary level of 
interest and concern by stakeholders. Although there is not currently, 
nor is there likely to be, a public health and safety issue, the NRC is 
conducting additional independent inspections and assessments of the 
licensee's activities, and has increased external stakeholder 
communications and outreach, to respond to stakeholder concerns and 
maintain public confidence.
    The NRC staff considers the ROP adequate for ensuring public health 
and safety and notes that the groundwater contamination at VY does not 
pose a public health or safety hazard.
    The staff further notes that it has exercised its authority to 
deviate from the ROP Action Matrix to be responsive to unique 
circumstances and stakeholder concerns. The NRC staff conducts annual 
ROP self-assessments, which include evaluations of deviations from the 
Action matrix to see if improvements are warranted in the ROP. The 
results of the calendar year 2010 self-assessment will be included in 
the annual Commission paper and metric report, which will be issued in 
early April of 2011 and discussed during the Agency Action Review 
Meeting (AARM): a meeting of senior NRC managers to confirm the results 
and effectiveness of the ROP. The results of the AARM will be presented 
to the Commission in a public meeting in May 2011.
5. Concern 5--VY's Decommissioning Fund Is Inadequate Due to the 
Increase in Decommissioning Costs
    NRC establishes requirements for licensees to provide reasonable 
assurance that funds will be available for the decommissioning process. 
Reasonable assurance consists of a series of steps outlined in 10 CFR 
50.75, ``Reporting and record keeping for decommissioning planning.'' 
VY must

[[Page 15001]]

file an annual report to the NRC containing a certification that 
financial assurance for decommissioning will be or has been provided in 
an amount which may be more, but not less than, the amount stated in 
the regulations, adjusted as appropriate for changes in labor, energy, 
and waste burial costs. The formula for adequate decommissioning funds 
includes an estimated waste disposal volume based on the plant design. 
The actual waste disposal volume may increase due to a leak or spill at 
a level that requires remediation. The licensee is responsible for 
payment of any increased waste disposal costs, whether paid for out of 
the allocated funds from the decommissioning fund or other assets. The 
current remediation of the tritium in soil and groundwater at VY has 
been funded as an operating expense and no money was used from the 
decommissioning trust fund. VY previously submitted a site-specific 
decommissioning cost analysis, which was approved by the NRC by letter 
dated February 3, 2009 (ADAMS Accession No. ML083390193). VY must 
address any required changes in their next annual report. Because no 
violations of NRC requirements were identified, enforcement action is 
not warranted for this concern.

B. Additional NRC Actions Pertaining to Groundwater Contamination

    In March of 2010, NRC's EDO established a Groundwater Task Force 
(GTF) to review the NRCs approach to ground water contamination 
conditions, given the recent incidents of leaking buried pipes at 
commercial nuclear power plants. The charter of the Task Force was to 
reevaluate the recommendations made in the Liquid Radioactive Release 
Lessons Learned Task Force Final Report dated September 1, 2006 (ADAMS 
Accession No. ML062650312); review the actions taken in Commission 
Paper SECY-09-0174 ``Staff Progress in Evaluation of Buried Piping at 
Nuclear Reactor Facilities'' (ADAMS Accession No. ML093160004); and 
review the actions taken in response to recent releases of tritium into 
groundwater by nuclear facilities.
    The GTF completed its work in June 2010 and provided its report to 
the EDO. The report characterized a variety of issues ranging from 
policy issues to communications improvement opportunities. The complete 
report may be found under ADAMS Accession No. ML101740509. The GTF 
determined that the NRC is accomplishing its stated mission of 
protecting public health, safety, and protection of the environment 
through its response to groundwater leaks/spills. Within the current 
regulatory structure, the NRC is correctly applying requirements and 
properly characterizing the relevant issues. However, the GTF reported 
that there are further observations, conclusions, and recommendations 
that the NRC should consider in its oversight of groundwater 
contamination incidents.
    The EDO appointed a group of NRC senior executives to review the 
report and consider its findings. The group reviewed the GTF final 
report, including the conclusions, recommendations, and their bases. 
They identified conclusions and recommendations that do not involve 
policy issues, and tasked the NRC staff to address them. They have also 
identified policy issues, and a policy paper has been sent to the 
Commission discussing those issues.
    A public workshop was held on October 4, 2010, with external 
stakeholders to discuss the findings of the GTF Report and to receive 
input on the potential policy issues. In addition, a request for public 
comment was published in the Federal Register (75 FR 57987). These 
efforts help to ensure the NRC is considering the right issues on which 
to focus its attention as it moves forward. The transcript from this 
meeting is available on the NRC's Web site at: https://www.nrc.gov/reading-rm/doc-collections/fact-sheets/buried-pipes-tritium.html.

III. Conclusion

    As summarized above, the NRC staff did not identify any violations 
and the public health and safety remains reasonably assured. Thus, no 
enforcement action against VY is warranted. The NRC staff concludes 
that the petitioners' concerns have been addressed and resolved such 
that no further action is needed in response to the petitions.
    As provided in 10 CFR 2.206(c), a copy of this Director's Decision 
will be filed with the Secretary of the Commission for the Commission 
to review. As provided for by this regulation, the Decision will 
constitute the final action of the Commission 25 days after the date of 
the Decision unless the Commission, on its own motion, institutes a 
review of the Decision within that time.

    Dated at Rockville, Maryland, this 11th day of March 2011.

    For the Nuclear Regulatory Commission.
Eric J. Leeds,
Director, Office of Nuclear Reactor Regulation.
[FR Doc. 2011-6401 Filed 3-17-11; 8:45 am]
BILLING CODE 7590-01-P