Abnormal Occurrence Reports: Implementation of Section 208 of the Energy Reorganization Act of 1974; Revised Policy Statement, 10568-10570 [E6-2857]

Download as PDF 10568 Federal Register / Vol. 71, No. 40 / Wednesday, March 1, 2006 / Notices One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff; (3) E-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, hearingdocket@nrc.gov; or (4) facsimile transmission addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC, Attention: Rulemakings and Adjudications Staff at (301) 415–1101, verification number is (301) 415–1966. A copy of the request for hearing and petition for leave to intervene should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, and it is requested that copies be transmitted either by means of facsimile transmission to 301–415–3725 or by email to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to M. S. Ross, Managing Attorney, Florida Power & Light Company, P.O. Box 14000, Juno Beach, FL 33408–0420, attorney for the licensee. For further details with respect to this action, see the application for amendment dated February 21, 2006, which is available for public inspection at the Commission’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System’s (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site https://www.nrc.gov/ reading-rm.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1–800–397–4209, 301– 415–4737, or by e-mail to pdr@nrc.gov. Dated at Rockville, Maryland, this 23rd day of February 2006. For the Nuclear Regulatory Commission. Brendan T. Moroney, Project Manager, Plant Licensing Branch II– 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E6–2856 Filed 2–28–06; 8:45 am] wwhite on PROD1PC61 with NOTICES BILLING CODE 7590–01–P VerDate Aug<31>2005 18:25 Feb 28, 2006 Jkt 208001 NUCLEAR REGULATORY COMMISSION Abnormal Occurrence Reports: Implementation of Section 208 of the Energy Reorganization Act of 1974; Revised Policy Statement U.S. Nuclear Regulatory Commission. ACTION: Issuance of Revised Policy Statement on Abnormal Occurrence Criteria and Solicitation of Comments. AGENCY: SUMMARY: This policy statement presents the revised abnormal occurrence (AO) criteria the Commission uses for selecting AO’s for the annual report to Congress as required by section 208 of the Energy Reorganization Act of 1974 (Pub. L. 93– 438). Section 208 of the act defines an AO as an unscheduled incident or event which the U.S. Nuclear Regulatory Commission (NRC) determines to be significant from the standpoint of public health or safety. The AO criteria have been amended to ensure that the criteria are consistent with the NRC’s Strategic Plan for Fiscal Year (FY) 2004–2009 and the NRC rulemaking on Title 10, part 35, of the Code of Federal Regulations (10 CFR part 35), ‘‘Medical Use of Byproduct Material.’’ Additionally, riskinformed criteria based on the NRC Accident Sequence Precursor (ASP) Program and Reactor Oversight Process (ROP) have been added for selecting abnormal occurrences at commercial nuclear power plants for the report to Congress. The ASP program assesses the risk significance of issues and events. The ROP is a risk-informed, tiered approach to ensuring the safety of nuclear power plants. The ROP is a process for collecting information about licensee performance, assessing the safety significance of the information, taking appropriate actions, and ensuring that licensees correct deficiencies. Some sections of the AO criteria have been restructured. The restructuring accommodates the changes in the criteria and minimizes duplication. Any interested party may submit comments on the criteria for the NRC staff’s consideration. The comments should include supporting information. DATES: Submit comments by May 30, 2006. Comments received after this date will be considered if it is practicable to do so, but cannot be assured consideration. ADDRESSES: You may submit comments by any one of the following methods. Comments submitted in writing or electronic form will be made available for public inspection. Mail comments to Secretary, U.S. Nuclear Regulatory PO 00000 Frm 00107 Fmt 4703 Sfmt 4703 Commission, Washington, DC 20555– 0001, ATTN: Rulemakings and Adjudications Staff. E-mail comments to SECY@nrc.gov. If you do not receive a reply e-mail confirming that we have received your comments, call us at (301) 415–1966. Hand-deliver comments to 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on Federal workdays (telephone (301) 415–1966). Fax comments to Secretary, U.S. Nuclear Regulatory Commission, at (301) 415– 1101. Publicly available documents may be viewed electronically on the public computers at the NRC’s Public Document Room (PDR), One White Flint North, 11555 Rockville Pike, Room O1– F21, Rockville, Maryland. The PDR reproduction contractor will copy documents for a fee. The public can access the NRC’s Agencywide Documents Access and Management System (ADAMS) through the agency’s public Web site at https://www.nrc.gov. This Web site provides text and image files of the NRC’s public documents. If you do not have access to ADAMS or have problems in accessing the documents in ADAMS, contact the NRC PDR reference staff at 1–800–397–4209 or 301–415–4737 or by e-mail to pdr@nrc.gov. FOR FURTHER INFORMATION CONTACT: Sheryl Burrows, telephone: (301) 415– 6086; e-mail: SAB2@nrc.gov; USNRC, Office of Nuclear Regulatory Research, Mail Stop T9–F31, Washington, DC 20555–0001. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O–1 F21, Rockville, Maryland. SUPPLEMENTARY INFORMATION: I. Background Section 208 of the Energy Reorganization Act of 1974 (Pub. L. 93– 438) defines an abnormal occurrence (AO) as an unscheduled incident or event which the U.S. Nuclear Regulatory Commission (NRC) determines to be significant from the standpoint of public health or safety. The Federal Reports Elimination and Sunset Act of 1995 (Pub. L. 104–66) requires that AOs be reported to Congress annually. Section 208 requires that the discussion of each event include the date and place, the nature and probable consequences, the cause or causes, and the action taken to prevent recurrence. The Commission must also widely disseminate the AO report to the E:\FR\FM\01MRN1.SGM 01MRN1 Federal Register / Vol. 71, No. 40 / Wednesday, March 1, 2006 / Notices public within 15 days of sending it to Congress. Abnormal Occurrence Reporting The AO policy statement has been developed to comply with Section 208 of the Energy Reorganization Act of 1974, as amended. The intent of the act is to keep Congress and the public informed of unscheduled incidents or events which the Commission considers significant from the standpoint of public health and safety. The policy reflects a range of health and safety concerns and applies to incidents and events involving a single individual, as well as those having overall impact on the general public. The AO criteria uses a high reporting threshold to report to Congress only those events considered significant from the standpoint of public health and safety. Licensee Reports This general policy statement will not change the reporting requirements for NRC licensees in Commission regulations, license conditions, or technical specifications (TS). NRC licensees will continue to submit required reports on a wide range of events, including instrument malfunctions and deviations from normal operating procedures that are not significant from the standpoint of the public health and safety but provide data useful to the Commission in monitoring operating trends at licensed facilities and in comparing the actual performance of the facilities with their design and/or licensing basis. wwhite on PROD1PC61 with NOTICES Applicability Implementation of section 208 of the Energy Reorganization Act of 1974, as amended, ‘‘Abnormal Occurrence Reports’’, involves the conduct of Commission business and does not impose requirements on licensees or certified facilities. The reports cover certain unscheduled incidents or events related to the manufacture, construction, or operation of a facility or conduct of an activity subject to the requirements of parts 20, 30 through 36, 39, 40, 50, 61, 70, 71, 72 or 76 of Chapter I of Title 10 of the Code of Federal Regulations (10 CFR). Agreement States provide information to the NRC on incidents and events involving applicable nuclear materials in their States. Events reported by Agreements States that reach the threshold for reporting as AOs are also published in the ‘‘Report to Congress on Abnormal Occurrences.’’ VerDate Aug<31>2005 18:25 Feb 28, 2006 Jkt 208001 Abnormal Occurrence General Statement of Policy The Commission will apply the following policy in determining whether an incident or event at a facility or involving an activity that is licensed or otherwise regulated by the Commission is an AO. An incident or event is considered an AO if it involves a major reduction in the protection of public health or safety. The incident or event has a moderate or severe impact on public health or safety and could include, but need not be limited to, the following: (1) Moderate exposure to, or release of, radioactive material licensed or otherwise regulated by the Commission, (2) Major degradation of essential safety-related equipment, or (3) Major deficiencies in the design, construction, or use of management controls for facilities or radioactive material. The criteria for determining whether to consider an incident or event for reporting as an AO are set forth in Appendix A of this policy statement. Commission Dissemination of AO Information The Commission widely disseminates the AO reports to the public. The Commission submits an annual report to Congress on AOs at or associated with any facility or activity which is licensed or otherwise regulated pursuant to the Atomic Energy Act of 1954, as amended, or the Energy Reorganization Act of 1974, as amended. This report gives the date, place, nature, and probable consequences of each AO, the cause or causes of each AO, and any actions taken to prevent recurrence. Appendix A: Abnormal Occurrence Criteria The following criteria are used to determine whether to consider events for reporting as AOs: I. For All Licensees A. Human Exposure to Radiation from Licensed Material. 1. Any unintended radiation exposure to an adult (any individual 18 years of age or older) resulting in an annual total effective dose equivalent (TEDE) of 250 mSv (25 rem) or more; or an annual sum of the deep dose equivalent (external dose) and committed dose equivalent (intake of radioactive material) to any individual organ other than the lens of the eye, the bone marrow, and the gonads of 2,500 mSv (250 rem) or more; or an annual dose equivalent to the lens of the eye of 1 Sv (100 rem) or more; or an annual sum of the deep dose equivalent and committed dose equivalent to the bone marrow of 1 Sv (100 rem) or more; or a committed dose equivalent to the gonads of 2,500 mSv (250 rem) or more; or an annual PO 00000 Frm 00108 Fmt 4703 Sfmt 4703 10569 shallow-dose equivalent to the skin or extremities of 2,500 mSv (250 rem) or more. 2. Any unintended radiation exposure to any minor (an individual less than 18 years of age) resulting in an annual TEDE of 50 mSv (5 rem) or more, or to an embryo/fetus resulting in a dose equivalent of 50 mSv (5 rem) or more. 3. Any radiation exposure that has resulted in unintended permanent functional damage to an organ or a physiological system as determined by a physician. B. Discharge or dispersal of radioactive material from its intended place of confinement which results in the release of radioactive material to an unrestricted area in concentrations which, if averaged over a period of 24 hours, exceeds 5,000 times the values specified in Table 2 of Appendix B to 10 CFR part 20, unless the licensee has demonstrated compliance with § 20.1301 using § 20.1302(b)(1) or § 20.1302(b)(2)(ii). This criterion does not apply to transportation events. C. Theft, Diversion, or Loss of Licensed Material, or Sabotage or Security Breach.1 1. Any unrecovered lost, stolen, or abandoned sources that exceed the values listed in Appendix P to Part 110, ‘‘High Risk Radioactive Material, Category 2.’’ Excluded from reporting under this criterion are those events involving sources that are lost, stolen, or abandoned under the following conditions: Sources abandoned in accordance with the requirements of 10 CFR 39.77(c); sealed sources contained in labeled, rugged source housings; recovered sources with sufficient indication that doses in excess of the reporting thresholds specified in AO criteria I.A.1 and I.A.2 did not occur while the source was missing; and unrecoverable sources (sources that have been lost and for which a reasonable attempt at recovery has been made without success) lost under such conditions that doses in excess of the reporting thresholds specified in AO criteria I.A.1 and I.A.2 are not known to have occurred and the agency has determined that the risk of theft or diversion is acceptably low. 2. A substantiated case of actual or attempted theft or diversion of licensed material or sabotage of a facility. 3. Any substantiated loss of special nuclear material or any substantiated inventory discrepancy that is judged to be significant relative to normally expected performance and that is judged to be caused by theft or diversion or by a substantial breakdown of the accountability system. 4. Any substantial breakdown of physical security or material control (i.e., access control containment or accountability systems) that significantly weakened the 1 Information pertaining to certain incidents may be either classified or under consideration for classification because of national security implications. Classified information will be withheld when formally reporting these incidents in accordance with section 208 of the ERA of 1974, as amended. Any classified details regarding these incidents would be available to the Congress, upon request, under appropriate security arrangements. E:\FR\FM\01MRN1.SGM 01MRN1 10570 Federal Register / Vol. 71, No. 40 / Wednesday, March 1, 2006 / Notices protection against theft, diversion, or sabotage.2 5. Any significant unauthorized disclosures (loss, theft, and/or deliberate) of classified and/or safeguards information that harm national security. D. Initiation of High-Level NRC Team Inspections.3 wwhite on PROD1PC61 with NOTICES II. For Commercial Nuclear Power Plant Licensees A. Malfunction of Facility, Structures, or Equipment. 1. Exceeding a safety limit of license technical specification (TS) [10 CFR 50.36(c)]. 2. Serious degradation of fuel integrity, primary coolant pressure boundary, or primary containment boundary. 3. Loss of plant capability to perform essential safety functions so that a release of radioactive materials which could result in exceeding the dose limits of 10 CFR part 100 or 5 times the dose limits of 10 CFR part 50, Appendix A, General Design Criterion (GDC) 19, could occur from a postulated transient or accident (e.g., loss of emergency core cooling system, loss of control rod system). B. Design or Safety Analysis Deficiency, Personnel Error, or Procedural or Administrative Inadequacy. 1. Discovery of a major condition not specifically considered in the safety analysis report (SAR) or TS that requires immediate remedial action. 2. Personnel error or procedural deficiencies that result in loss of plant capability to perform essential safety functions so that a release of radioactive materials which could result in exceeding the dose limits of 10 CFR part 100 or 5 times the dose limits of 10 CFR part 50, Appendix A, GDC 19, could occur from a postulated transient or accident (e.g., loss of emergency core cooling system, loss of control rod drive mechanism). C. Any reactor events or conditions that are determined to be of high safety significance.4 D. Any operating reactor plants that are determined to have overall unacceptable performance or that are in a shutdown 2 Due to increased terrorist activities worldwide, the AO report would not disclose specific classified information and sensitive information, the details of which are considered useful to a potential terrorist. Classified information is defined as information that would harm national security if disclosed in an unauthorized manner. 3 Initiation of any Incident Investigation Teams, as described in NRC Management Directive (MD) 8.3, ‘‘NRC Incident Investigation Program,’’ or initiation of any Accident Review Groups, as described in MD 8.9, ‘‘Accident Investigation.’’ 4 The NRC ROP uses four colors to describe the safety significance of licensee performance. As defined in NRC Management Directive 8.13, ‘‘Reactor Oversight Process,’’ green is used for very low safety significance, white is used for low to moderate safety significance, yellow is used for substantial safety significance, and red is used for high safety significance. Reactor conditions or performance indicators evaluated to be red are considered Abnormal Occurrences. Additionally, Criterion II.C also includes any events or conditions evaluated by the NRC ASP program to have a conditional core damage probability (CCDP) or change in core damage probability (DCDP) of greater than 1×10¥3. VerDate Aug<31>2005 18:25 Feb 28, 2006 Jkt 208001 condition as a result of significant performance problems and/or operational event(s).5 III. Events at Facilities Other Than Nuclear Power Plants and All Transportation Events A. Events Involving Design, Analysis, Construction, Testing, Operation, Transport, Use, or Disposal of Licensed Facilities or Regulated Materials 1. An accidental criticality [10 CFR 70.52(a)]. 2. A major deficiency in design, construction, control, or operation having significant safety implications that require immediate remedial action. 3. A serious safety-significant deficiency in management or procedural controls. 4. A series of events (in which the individual events are not of major importance), recurring incidents, or incidents with implications for similar facilities (generic incidents) that raise a major safety concern. B. For Fuel Cycle Facilities 1. Absence or failure of all safety-related or security-related controls (engineered and human) for an NRC-regulated lethal hazard (radiological or chemical) while the lethal hazard is present. 2. An NRC-ordered safety-related or security-related immediate remedial action. C. For Medical Licensees A medical event that: 1. Results in a dose that is: a. Equal to or greater than 1Gy (100 rad) to a major portion of the bone marrow or to the lens of the eye; or equal or greater than 2.5 Gy (250 rad) to the gonads; or b. Equal to or greater than 10 Gy (1,000 rad) to any other organ or tissue; and 2. Represents either: a. A dose or dosage that is at least 50 percent greater than that prescribed, or b. A prescribed dose or dosage that: (i) Is the wrong radiopharmaceutical or unsealed byproduct material; or (ii) Is delivered by the wrong route of administration; or (iii) Is delivered to the wrong treatment site; or (iv) Is delivered by the wrong treatment mode; or (v) Is from a leaking source or sources; or (vi) Is delivered to the wrong individual or human research subject. IV. Other Events of Interest The Commission may determine that events other than AOs may be of interest to Congress and the public and should be included in an appendix to the AO report as ‘‘Other Events of Interest.’’ Such events include, but are not necessarily limited to, events that do not meet the AO criteria but that have been perceived by Congress or the public to be of high health and safety 5 Any plants assessed by the ROP to be in the unacceptable performance column, as described in NRC Inspection Manual Chapter 0305, ‘‘Operating Reactor Assessment Program.’’ This assessment of safety performance is based on the number and significance of NRC inspection findings and licensee performance indicators. PO 00000 Frm 00109 Fmt 4703 Sfmt 4703 significance, have received significant media coverage, or have caused the NRC to increase its attention to or oversight of a program area, or a group of similar events as a result of which licensed materials entered the public domain in an uncontrolled manner. [5 U.S.C. 552(a)]. Dated at Rockville, Maryland, this 23rd day of February, 2006. For the U.S. Nuclear Regulatory Commission. Annette L. Vietti-Cook, Secretary of the Commission. [FR Doc. E6–2857 Filed 2–28–06; 8:45 am] BILLING CODE 7590–01–P SECURITIES AND EXCHANGE COMMISSION Proposed Collection; Comment Request Upon written request, copy available from: Securities and Exchange Commission, Office of Filings and Information Services, Washington, DC 20549. Extension: Form N–54C; SEC File No. 270–184; OMB Control No. 3235–0236. Notice is hereby given that, pursuant to the Paperwork Reduction Act of 1995 [44 U.S.C. 3501 et seq.] (the ‘‘Act’’), the Securities and Exchange Commission (the ‘‘Commission’’) is soliciting comments on the collection of information summarized below. The Commission plans to submit this existing collection of information to the Office of Management and Budget for extension and approval. Form N–54C under the Investment Company Act of 1940 [17 CFR 274.54] is a notification to the Commission that a company withdraws its election to be regulated as a business development company. Such a company only has to file a Form N–54C once. It is estimated that approximately 18 respondents per year file with the Commission a Form N–54C. Form N– 54C requires approximately 1 burden hour per response resulting from creating and filing the information required by the Form. The total burden hours for Form N–54C would be 18 hours per year in the aggregate. The estimated annual burden of 18 hours represents an increase of 10 hours over the prior estimate of 8 hours. The increase in burden hours is attributable to an increase in the number of respondents from 8 to 18. The estimate of average burden hours for Form N54–C is made solely for the purposes of the Act and is not derived from a comprehensive or even E:\FR\FM\01MRN1.SGM 01MRN1

Agencies

[Federal Register Volume 71, Number 40 (Wednesday, March 1, 2006)]
[Notices]
[Pages 10568-10570]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-2857]


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NUCLEAR REGULATORY COMMISSION


Abnormal Occurrence Reports: Implementation of Section 208 of the 
Energy Reorganization Act of 1974; Revised Policy Statement

AGENCY: U.S. Nuclear Regulatory Commission.

ACTION: Issuance of Revised Policy Statement on Abnormal Occurrence 
Criteria and Solicitation of Comments.

-----------------------------------------------------------------------

SUMMARY: This policy statement presents the revised abnormal occurrence 
(AO) criteria the Commission uses for selecting AO's for the annual 
report to Congress as required by section 208 of the Energy 
Reorganization Act of 1974 (Pub. L. 93-438). Section 208 of the act 
defines an AO as an unscheduled incident or event which the U.S. 
Nuclear Regulatory Commission (NRC) determines to be significant from 
the standpoint of public health or safety. The AO criteria have been 
amended to ensure that the criteria are consistent with the NRC's 
Strategic Plan for Fiscal Year (FY) 2004-2009 and the NRC rulemaking on 
Title 10, part 35, of the Code of Federal Regulations (10 CFR part 35), 
``Medical Use of Byproduct Material.'' Additionally, risk-informed 
criteria based on the NRC Accident Sequence Precursor (ASP) Program and 
Reactor Oversight Process (ROP) have been added for selecting abnormal 
occurrences at commercial nuclear power plants for the report to 
Congress. The ASP program assesses the risk significance of issues and 
events. The ROP is a risk-informed, tiered approach to ensuring the 
safety of nuclear power plants. The ROP is a process for collecting 
information about licensee performance, assessing the safety 
significance of the information, taking appropriate actions, and 
ensuring that licensees correct deficiencies. Some sections of the AO 
criteria have been restructured. The restructuring accommodates the 
changes in the criteria and minimizes duplication. Any interested party 
may submit comments on the criteria for the NRC staff's consideration. 
The comments should include supporting information.

DATES: Submit comments by May 30, 2006. Comments received after this 
date will be considered if it is practicable to do so, but cannot be 
assured consideration.

ADDRESSES: You may submit comments by any one of the following methods. 
Comments submitted in writing or electronic form will be made available 
for public inspection. Mail comments to Secretary, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, ATTN: Rulemakings and 
Adjudications Staff. E-mail comments to SECY@nrc.gov. If you do not 
receive a reply e-mail confirming that we have received your comments, 
call us at (301) 415-1966. Hand-deliver comments to 11555 Rockville 
Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on 
Federal workdays (telephone (301) 415-1966). Fax comments to Secretary, 
U.S. Nuclear Regulatory Commission, at (301) 415-1101.
    Publicly available documents may be viewed electronically on the 
public computers at the NRC's Public Document Room (PDR), One White 
Flint North, 11555 Rockville Pike, Room O1-F21, Rockville, Maryland. 
The PDR reproduction contractor will copy documents for a fee. The 
public can access the NRC's Agencywide Documents Access and Management 
System (ADAMS) through the agency's public Web site at https://
www.nrc.gov. This Web site provides text and image files of the NRC's 
public documents. If you do not have access to ADAMS or have problems 
in accessing the documents in ADAMS, contact the NRC PDR reference 
staff at 1-800-397-4209 or 301-415-4737 or by e-mail to pdr@nrc.gov.

FOR FURTHER INFORMATION CONTACT: Sheryl Burrows, telephone: (301) 415-
6086; e-mail: SAB2@nrc.gov; USNRC, Office of Nuclear Regulatory 
Research, Mail Stop T9-F31, Washington, DC 20555-0001.
    A copy of the final supporting statement may be viewed free of 
charge at the NRC Public Document Room, One White Flint North, 11555 
Rockville Pike, Room O-1 F21, Rockville, Maryland.

SUPPLEMENTARY INFORMATION: 

I. Background

    Section 208 of the Energy Reorganization Act of 1974 (Pub. L. 93-
438) defines an abnormal occurrence (AO) as an unscheduled incident or 
event which the U.S. Nuclear Regulatory Commission (NRC) determines to 
be significant from the standpoint of public health or safety. The 
Federal Reports Elimination and Sunset Act of 1995 (Pub. L. 104-66) 
requires that AOs be reported to Congress annually. Section 208 
requires that the discussion of each event include the date and place, 
the nature and probable consequences, the cause or causes, and the 
action taken to prevent recurrence. The Commission must also widely 
disseminate the AO report to the

[[Page 10569]]

public within 15 days of sending it to Congress.

Abnormal Occurrence Reporting

    The AO policy statement has been developed to comply with Section 
208 of the Energy Reorganization Act of 1974, as amended. The intent of 
the act is to keep Congress and the public informed of unscheduled 
incidents or events which the Commission considers significant from the 
standpoint of public health and safety. The policy reflects a range of 
health and safety concerns and applies to incidents and events 
involving a single individual, as well as those having overall impact 
on the general public. The AO criteria uses a high reporting threshold 
to report to Congress only those events considered significant from the 
standpoint of public health and safety.

Licensee Reports

    This general policy statement will not change the reporting 
requirements for NRC licensees in Commission regulations, license 
conditions, or technical specifications (TS). NRC licensees will 
continue to submit required reports on a wide range of events, 
including instrument malfunctions and deviations from normal operating 
procedures that are not significant from the standpoint of the public 
health and safety but provide data useful to the Commission in 
monitoring operating trends at licensed facilities and in comparing the 
actual performance of the facilities with their design and/or licensing 
basis.

Applicability

    Implementation of section 208 of the Energy Reorganization Act of 
1974, as amended, ``Abnormal Occurrence Reports'', involves the conduct 
of Commission business and does not impose requirements on licensees or 
certified facilities. The reports cover certain unscheduled incidents 
or events related to the manufacture, construction, or operation of a 
facility or conduct of an activity subject to the requirements of parts 
20, 30 through 36, 39, 40, 50, 61, 70, 71, 72 or 76 of Chapter I of 
Title 10 of the Code of Federal Regulations (10 CFR).
    Agreement States provide information to the NRC on incidents and 
events involving applicable nuclear materials in their States. Events 
reported by Agreements States that reach the threshold for reporting as 
AOs are also published in the ``Report to Congress on Abnormal 
Occurrences.''

Abnormal Occurrence General Statement of Policy

    The Commission will apply the following policy in determining 
whether an incident or event at a facility or involving an activity 
that is licensed or otherwise regulated by the Commission is an AO.
    An incident or event is considered an AO if it involves a major 
reduction in the protection of public health or safety. The incident or 
event has a moderate or severe impact on public health or safety and 
could include, but need not be limited to, the following:
    (1) Moderate exposure to, or release of, radioactive material 
licensed or otherwise regulated by the Commission,
    (2) Major degradation of essential safety-related equipment, or
    (3) Major deficiencies in the design, construction, or use of 
management controls for facilities or radioactive material.
    The criteria for determining whether to consider an incident or 
event for reporting as an AO are set forth in Appendix A of this policy 
statement.

Commission Dissemination of AO Information

    The Commission widely disseminates the AO reports to the public. 
The Commission submits an annual report to Congress on AOs at or 
associated with any facility or activity which is licensed or otherwise 
regulated pursuant to the Atomic Energy Act of 1954, as amended, or the 
Energy Reorganization Act of 1974, as amended. This report gives the 
date, place, nature, and probable consequences of each AO, the cause or 
causes of each AO, and any actions taken to prevent recurrence.

Appendix A: Abnormal Occurrence Criteria

    The following criteria are used to determine whether to consider 
events for reporting as AOs:

I. For All Licensees

    A. Human Exposure to Radiation from Licensed Material.
    1. Any unintended radiation exposure to an adult (any individual 
18 years of age or older) resulting in an annual total effective 
dose equivalent (TEDE) of 250 mSv (25 rem) or more; or an annual sum 
of the deep dose equivalent (external dose) and committed dose 
equivalent (intake of radioactive material) to any individual organ 
other than the lens of the eye, the bone marrow, and the gonads of 
2,500 mSv (250 rem) or more; or an annual dose equivalent to the 
lens of the eye of 1 Sv (100 rem) or more; or an annual sum of the 
deep dose equivalent and committed dose equivalent to the bone 
marrow of 1 Sv (100 rem) or more; or a committed dose equivalent to 
the gonads of 2,500 mSv (250 rem) or more; or an annual shallow-dose 
equivalent to the skin or extremities of 2,500 mSv (250 rem) or 
more.
    2. Any unintended radiation exposure to any minor (an individual 
less than 18 years of age) resulting in an annual TEDE of 50 mSv (5 
rem) or more, or to an embryo/fetus resulting in a dose equivalent 
of 50 mSv (5 rem) or more.
    3. Any radiation exposure that has resulted in unintended 
permanent functional damage to an organ or a physiological system as 
determined by a physician.
    B. Discharge or dispersal of radioactive material from its 
intended place of confinement which results in the release of 
radioactive material to an unrestricted area in concentrations 
which, if averaged over a period of 24 hours, exceeds 5,000 times 
the values specified in Table 2 of Appendix B to 10 CFR part 20, 
unless the licensee has demonstrated compliance with Sec.  20.1301 
using Sec.  20.1302(b)(1) or Sec.  20.1302(b)(2)(ii). This criterion 
does not apply to transportation events.
    C. Theft, Diversion, or Loss of Licensed Material, or Sabotage 
or Security Breach.\1\
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    \1\ Information pertaining to certain incidents may be either 
classified or under consideration for classification because of 
national security implications. Classified information will be 
withheld when formally reporting these incidents in accordance with 
section 208 of the ERA of 1974, as amended. Any classified details 
regarding these incidents would be available to the Congress, upon 
request, under appropriate security arrangements.
---------------------------------------------------------------------------

    1. Any unrecovered lost, stolen, or abandoned sources that 
exceed the values listed in Appendix P to Part 110, ``High Risk 
Radioactive Material, Category 2.'' Excluded from reporting under 
this criterion are those events involving sources that are lost, 
stolen, or abandoned under the following conditions: Sources 
abandoned in accordance with the requirements of 10 CFR 39.77(c); 
sealed sources contained in labeled, rugged source housings; 
recovered sources with sufficient indication that doses in excess of 
the reporting thresholds specified in AO criteria I.A.1 and I.A.2 
did not occur while the source was missing; and unrecoverable 
sources (sources that have been lost and for which a reasonable 
attempt at recovery has been made without success) lost under such 
conditions that doses in excess of the reporting thresholds 
specified in AO criteria I.A.1 and I.A.2 are not known to have 
occurred and the agency has determined that the risk of theft or 
diversion is acceptably low.
    2. A substantiated case of actual or attempted theft or 
diversion of licensed material or sabotage of a facility.
    3. Any substantiated loss of special nuclear material or any 
substantiated inventory discrepancy that is judged to be significant 
relative to normally expected performance and that is judged to be 
caused by theft or diversion or by a substantial breakdown of the 
accountability system.
    4. Any substantial breakdown of physical security or material 
control (i.e., access control containment or accountability systems) 
that significantly weakened the

[[Page 10570]]

protection against theft, diversion, or sabotage.\2\
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    \2\ Due to increased terrorist activities worldwide, the AO 
report would not disclose specific classified information and 
sensitive information, the details of which are considered useful to 
a potential terrorist. Classified information is defined as 
information that would harm national security if disclosed in an 
unauthorized manner.
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    5. Any significant unauthorized disclosures (loss, theft, and/or 
deliberate) of classified and/or safeguards information that harm 
national security.
    D. Initiation of High-Level NRC Team Inspections.\3\
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    \3\ Initiation of any Incident Investigation Teams, as described 
in NRC Management Directive (MD) 8.3, ``NRC Incident Investigation 
Program,'' or initiation of any Accident Review Groups, as described 
in MD 8.9, ``Accident Investigation.''
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II. For Commercial Nuclear Power Plant Licensees

    A. Malfunction of Facility, Structures, or Equipment.
    1. Exceeding a safety limit of license technical specification 
(TS) [10 CFR 50.36(c)].
    2. Serious degradation of fuel integrity, primary coolant 
pressure boundary, or primary containment boundary.
    3. Loss of plant capability to perform essential safety 
functions so that a release of radioactive materials which could 
result in exceeding the dose limits of 10 CFR part 100 or 5 times 
the dose limits of 10 CFR part 50, Appendix A, General Design 
Criterion (GDC) 19, could occur from a postulated transient or 
accident (e.g., loss of emergency core cooling system, loss of 
control rod system).
    B. Design or Safety Analysis Deficiency, Personnel Error, or 
Procedural or Administrative Inadequacy.
    1. Discovery of a major condition not specifically considered in 
the safety analysis report (SAR) or TS that requires immediate 
remedial action.
    2. Personnel error or procedural deficiencies that result in 
loss of plant capability to perform essential safety functions so 
that a release of radioactive materials which could result in 
exceeding the dose limits of 10 CFR part 100 or 5 times the dose 
limits of 10 CFR part 50, Appendix A, GDC 19, could occur from a 
postulated transient or accident (e.g., loss of emergency core 
cooling system, loss of control rod drive mechanism).
    C. Any reactor events or conditions that are determined to be of 
high safety significance.\4\
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    \4\ The NRC ROP uses four colors to describe the safety 
significance of licensee performance. As defined in NRC Management 
Directive 8.13, ``Reactor Oversight Process,'' green is used for 
very low safety significance, white is used for low to moderate 
safety significance, yellow is used for substantial safety 
significance, and red is used for high safety significance. Reactor 
conditions or performance indicators evaluated to be red are 
considered Abnormal Occurrences. Additionally, Criterion II.C also 
includes any events or conditions evaluated by the NRC ASP program 
to have a conditional core damage probability (CCDP) or change in 
core damage probability ([Delta]CDP) of greater than 
1x10-3.
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    D. Any operating reactor plants that are determined to have 
overall unacceptable performance or that are in a shutdown condition 
as a result of significant performance problems and/or operational 
event(s).\5\
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    \5\ Any plants assessed by the ROP to be in the unacceptable 
performance column, as described in NRC Inspection Manual Chapter 
0305, ``Operating Reactor Assessment Program.'' This assessment of 
safety performance is based on the number and significance of NRC 
inspection findings and licensee performance indicators.
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III. Events at Facilities Other Than Nuclear Power Plants and All 
Transportation Events

A. Events Involving Design, Analysis, Construction, Testing, 
Operation, Transport, Use, or Disposal of Licensed Facilities or 
Regulated Materials

    1. An accidental criticality [10 CFR 70.52(a)].
    2. A major deficiency in design, construction, control, or 
operation having significant safety implications that require 
immediate remedial action.
    3. A serious safety-significant deficiency in management or 
procedural controls.
    4. A series of events (in which the individual events are not of 
major importance), recurring incidents, or incidents with 
implications for similar facilities (generic incidents) that raise a 
major safety concern.

B. For Fuel Cycle Facilities

    1. Absence or failure of all safety-related or security-related 
controls (engineered and human) for an NRC-regulated lethal hazard 
(radiological or chemical) while the lethal hazard is present.
    2. An NRC-ordered safety-related or security-related immediate 
remedial action.

C. For Medical Licensees

    A medical event that:
    1. Results in a dose that is:
    a. Equal to or greater than 1Gy (100 rad) to a major portion of 
the bone marrow or to the lens of the eye; or equal or greater than 
2.5 Gy (250 rad) to the gonads; or
    b. Equal to or greater than 10 Gy (1,000 rad) to any other organ 
or tissue; and
    2. Represents either:
    a. A dose or dosage that is at least 50 percent greater than 
that prescribed, or
    b. A prescribed dose or dosage that:
    (i) Is the wrong radiopharmaceutical or unsealed byproduct 
material; or
    (ii) Is delivered by the wrong route of administration; or
    (iii) Is delivered to the wrong treatment site; or
    (iv) Is delivered by the wrong treatment mode; or
    (v) Is from a leaking source or sources; or
    (vi) Is delivered to the wrong individual or human research 
subject.

IV. Other Events of Interest

    The Commission may determine that events other than AOs may be 
of interest to Congress and the public and should be included in an 
appendix to the AO report as ``Other Events of Interest.'' Such 
events include, but are not necessarily limited to, events that do 
not meet the AO criteria but that have been perceived by Congress or 
the public to be of high health and safety significance, have 
received significant media coverage, or have caused the NRC to 
increase its attention to or oversight of a program area, or a group 
of similar events as a result of which licensed materials entered 
the public domain in an uncontrolled manner. [5 U.S.C. 552(a)].

    Dated at Rockville, Maryland, this 23rd day of February, 2006.

    For the U.S. Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.

 [FR Doc. E6-2857 Filed 2-28-06; 8:45 am]
BILLING CODE 7590-01-P
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