Production and utilization facilities; domestic licensing: Fire protection; post-fire operator manual actions; withdrawn,
[Federal Register: March 6, 2006 (Volume 71, Number 43)]
[Proposed Rules]
[Page 11169-11172]
From the Federal Register Online via GPO Access [wais.access.gpo.gov]
[DOCID:fr06mr06-12]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 50
RIN 3150 AH54
Fire Protection Program--Post-Fire Operator Manual Actions
AGENCY: Nuclear Regulatory Commission.
ACTION: Withdrawal of proposed rule.
SUMMARY: The Nuclear Regulatory Commission (NRC) is withdrawing its proposed amendment to the Commission's fire protection regulations for nuclear power facilities operating prior to January 1, 1979. The proposed amendment pertained to the use of manual actions by plant operators coincident with fire detectors and an installed automatic fire suppression system in the fire area as an alternative method to achieve hot shutdown conditions in the event of fires in certain plant areas. Based on stakeholder comments, the Commission believes that the proposed rule would not achieve intended objectives of effectiveness and efficiency.
FOR FURTHER INFORMATION CONTACT: David Diec, (301) 415-2834, e-mail dtd@nrc.gov or Alexander Klein, (301) 415-3477, e-mail ark1@nrc.gov of
the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission.
SUPPLEMENTARY INFORMATION
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Purpose II. Background III. Proposed Rulemaking IV. Withdrawal of Rulemaking V. Operator Manual Actions Closure Plan
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Ensuring Compliance
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Regulatory Issue Summary
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Staff Regulatory Review Guidelines
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Enforcement Action
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Purpose
For the reasons discussed in this document, the Commission is withdrawing a proposed rulemaking that was recommended as the appropriate regulatory tool to resolve a compliance issue associated with the use of operator manual actions for post-fire safe shutdown of nuclear power plants. The Commission is initiating a closure plan to ensure continuing compliance with the fire protection regulations.
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Background
Section 50.48(b) of the Code of Federal Regulations (10 CFR 50.48(b)) backfits the requirements of paragraphs III.G, III.J, and III.O of Appendix R, ``Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979,'' to 10 CFR part 50, ``Domestic Licensing of Production and Utilization Facilities,'' to plants licensed to operate before January 1, 1979 (pre-1979). The NRC incorporated similar guidance and criteria into Branch Technical Position CMEB 9.5-1, ``Guidelines for Fire Protection for Nuclear Power Plants,'' and section 9.5.1, ``Fire Protection Program,'' of NUREG- 0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' (also referred to as the Standard Review Plan (SRP) for plants licensed after January 1, 1979 (post-1979). Post- 1979 licensees incorporated their fire protection program implementation requirements into their operating licenses as license conditions.
Paragraph III.G.2 of Appendix R to 10 CFR part 50 requires that, where cables or equipment of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located in the same fire area, one of the following means of ensuring that one of the redundant trains is free of fire damage shall be provided:
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Separation of cables and equipment by a fire barrier having a 3- hour rating.
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Separation of cables and equipment by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards and with fire detectors and an automatic fire suppression system in the fire area.
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Enclosure of cables and equipment in a fire barrier having a 1- hour rating and with fire detectors and an automatic fire suppression system in the fire area.
Paragraph III.G.2 of Appendix R to 10 CFR part 50 cannot be reasonably interpreted to permit reliance upon operator manual actions in lieu of the specific methods provided in subparagraphs (a), (b), and/or (c) to ensure that one of the redundant safe shutdown trains in the same fire area is free of fire damage. Therefore, any pre-1979 licensee that is using operator manual actions instead of the specific methods in subparagraphs (a), (b), and/or (c) without an NRC-approved exemption is not in compliance with the regulations.
The staff became aware that some licensees were using operator manual actions in lieu of the requirements in Paragraph III.G.2 in Appendix R to 10 CFR part 50 and initiated this rulemaking as a means to bring plants into compliance.
10 CFR 50.12, ``Specific Exemptions,'' provides the basis for the NRC to consider exemptions from requirements in 10 CFR part 50, including the requirements in 10 CFR part 50, Appendix R.
In the past, the staff reviewed and approved a number of exemption requests for the use of operator manual actions when licensees could not meet the requirements for either separation distance, a fire barrier, or a fire suppression system as detailed under paragraphs III.G.2(a), (b), or (c) of Appendix R to 10 CFR Part 50. The staff's rationale for approving these exemptions was predicated on the type and amount of combustibles, the need for automatic fire suppression and detection capability, the effectiveness of the applicant's manual firefighting capability, and the time assumed available for plant operators to take such manual actions.
The regulations also allow licensees to use a risk-informed, performance-based approach under 10 CFR 50.48(c). This approach would allow licensees to use the National Fire Protection Association (NFPA) Standard 805, ``Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition,'' in lieu of seeking an exemption or license amendment or meeting the requirements of Appendix R.
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Proposed Rulemaking
In SECY-03-0100, ``Rulemaking Plan on Post-Fire Operator Manual Actions,'' dated June 17, 2003, the NRC staff recommended a revision to the reactor fire protection regulation contained in Appendix R to 10 CFR part 50 and associated guidance to resolve a regulatory compliance issue. The proposed rule on post-fire operator manual actions was published in the Federal Register on March 7, 2005 (70 FR 10901), with a 75-day comment period that ended on May 23, 2005. The proposed rule would have revised paragraph III.G.2 of Appendix R to allow licensees to implement acceptable operator manual actions combined with fire detectors and automatic fire suppression capability as an acceptable method for ensuring the capability of a licensee to bring a reactor to, and maintain it in, a hot shutdown condition. Fire detectors and automatic fire suppression requirements were included with the criteria for feasible and reliable operator manual actions to maintain fire protection defense-in-depth. The anticipated outcome of this proposed rule was to reduce unnecessary regulatory burden and maintain NRC effectiveness and efficiency by reducing the need for licensees to prepare exemption requests, and the need for NRC to review and approve these requests.
The NRC received about 80 comments from 14 individuals and organizations on the proposed rule. Industry stakeholders and the Nuclear Energy Institute (NEI) commented that the proposed rule requirement for an automatic fire suppression system is not necessary and installation of such systems would be costly without a clear safety enhancement. Industry stakeholders and NEI stated that this requirement would likely not reduce or eliminate the number of exemption requests, and thus, would not meet one of the primary purposes of the rulemaking.
Industry stakeholders further objected to the proposed rule requirement for a time margin and stated that thermal hydraulic calculations and other analyses have inherent conservatism that accounts for time margin. Industry stakeholders also objected to the time margin factor of two, stating that it is arbitrary, unprecedented, and inconsistent with requirements for other plant programs, such as emergency operating procedures.
Some industry stakeholders claim that the proposed rule is a backfit and that NRC guidance has allowed the use of operator manual actions to protect redundant safe shutdown trains.
Comments received from public interest groups and individuals generally stressed the need for the NRC to maintain the current regulations on fire protection of nuclear power plant safe shutdown capability. The Union of Concerned Scientists and the Nuclear Information and Resource Service stated that they agree with the staff's recommendation to withdraw the proposed rule.
The NRC's evaluation of the stakeholder comments is provided in
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the document titled ``Response to Public Comments on the Proposed Operator Manual Actions Rule.'' This document is available in ADAMS under ADAMS Accession No. ML053350235. ADAMS may be accessed via the NRC's Public Web site at http://www.nrc.gov/NRC/ADAMS/index.html.
The NRC has engaged stakeholders throughout the rulemaking process. On April 27, 2005, the NRC held a Category 3 public meeting at NRC Headquarters in Rockville, Maryland, to obtain stakeholder feedback on the proposed rule. Representatives from the industry, the Nuclear Energy Institute, industry consultants, and a public interest group attended the meeting. The feedback provided by stakeholders during the public meeting was similar in nature and consistent with those provided in written comments at the close of the 75-day public comment period.
On September 30, 2005, the NRC held a Category 2 public meeting at NRC Headquarters to discuss both the planned withdrawal of the proposed rule on post-fire operator manual actions and NRC's closure plan following withdrawal of the rule. During this meeting, the NRC received public comments on the closure plan from industry, the NEI, the Nuclear Information and Resource Service, and an industry consultant.
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Withdrawal of Rulemaking
Industry stakeholders and NEI stated that the proposed rule, if implemented, would require numerous exemption requests for conditions that do not satisfy the automatic fire suppression requirement, specific acceptance criteria for operator manual actions, or a combination thereof. This outcome would not be consistent with the primary purpose of the rulemaking which was to enhance effectiveness and efficiency by reducing or eliminating exemption requests. Therefore, the NRC is withdrawing the proposed rulemaking.
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Operator Manual Actions Closure Plan
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Ensuring Compliance
The NRC will continue to verify compliance with its regulations through scheduled inspections. The NRC expects noncompliances identified by NRC inspectors or licensees to be addressed by licensees through plant corrective actions.
The withdrawal of the operator manual actions rulemaking may require some licensees to take corrective actions that may be different from those described in the proposed rule. As such, the NRC's closure plan to deal with the rule withdrawal includes issuing a new regulatory issue summary and developing internal staff regulatory review guidelines for post-fire operator manual actions.
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Regulatory Issue Summary
The NRC intends to issue a regulatory issue summary (RIS) to reiterate the 10 CFR part 50, Appendix R Paragraph III.G.2 compliance expectations with respect to the use of operator manual actions, discuss the means to achieve compliance, advise licensees of the date the NRC will terminate the enforcement discretion guidance in Enforcement Guide Memorandum (EGM) 98-02, ``Enforcement Guidance Memorandum--Disposition of Violations Of Appendix R, Sections III.G and III.L Regarding Circuit Failures,'' Revision 2 issued in February 2000 (incorporated into Enforcement Manual section 8.1.7.1), and discuss potential exemption requests, compensatory measures and corrective actions pertaining to operator manual actions.
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Staff Regulatory Review Guidelines
The NRC developed acceptance criteria as part of the proposed rule for operator manual actions and also for DG-1136, ``Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire,'' dated February 2005, that provided an acceptable method for complying with the proposed rule. The acceptance criteria and DG-1136 were published in 70 FR 10901. The NRC plans to update section 9.5.1, ``Fire Protection Program,'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants'' [also referred to as the Standard Review Plan (SRP)] to address post-fire operator manual actions acceptance guidance. This update to the SRP will include the knowledge gained during the proposed rule development and will enhance the NRC regulatory review process for future licensing actions, such as exemption requests.
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Enforcement Action
In March 1998, the NRC staff issued EGM 98-02, which provides enforcement discretion guidance for issues related to fire-induced circuit failures. The most recent revision of EGM 98-02 was issued in February 2000 and can be accessed in ADAMS under ADAMS Accession Number ML003710123. This EGM, which remains in effect, discusses fire-induced circuit failure requirements and encompasses the vast majority of manual actions since manual actions are used as compensatory measures to satisfy the regulatory requirements related to fire-induced circuit failures. The EGM provides guidance for disposition of noncompliances involving fire-induced circuit failures, which could prevent operation or cause maloperation of equipment needed to achieve and maintain post- fire safe shutdown. The EGM includes guidance to provide discretion for cases where licensees do not dispute that a violation of regulatory requirements has occurred with respect to a nonconformance, take prompt compensatory actions, and take corrective actions within a reasonable time. The expectations of this EGM have been incorporated into the current NRC Enforcement Manual.
The Office of Nuclear Reactor Regulation issued a revised Inspection Procedure (IP) 71111.05T, ``Fire Protection (Triennial),'' in March 2003 providing inspection criteria for operator manual actions. The inspection criteria are used as guidance by NRC inspectors to determine if operator manual actions can be used as a compensatory measure while corrective actions are taken by the licensee.
The NRC plans to terminate the enforcement discretion guidance in EGM 98-02 6 months after the publication date of this Federal Register notice. During this 6-month period, the application of the enforcement guidance in EGM 98-02 in combination with the criteria in IP 71111.05T will ensure the adequacy and appropriateness of compensatory measures in the form of operator manual actions implemented in accordance with the licensee's fire protection program. Manual actions that fail to meet the criteria in the inspection procedure are not considered to be feasible or adequate compensatory measures. The continuation of enforcement discretion guidance for six months is intended to provide a reasonable amount of time for licensees that have implemented feasible and reliable operator manual actions as compensatory measures to initiate corrective actions. The corrective actions could involve compliance with III.G.2 or III.G.3; adoption of NFPA 805 through 10 CFR 50.48(c); or submission of exemption requests or license amendments.
Licensees that have initiated corrective actions within the 6-month period, for noncompliances involving operator manual actions used to address fire-induced circuit failures, will receive enforcement discretion for those noncompliances provided licensees complete the corrective actions in a timely manner. The NRC expects timely completion of the corrective actions
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consistent with RIS 2005-20, ``Revision to Guidance Formerly Contained in NRC Generic Letter 91-18,'' dated September 26, 2005 (ADAMS Accession No. ML052020424) not to exceed 3 years from the date of this Federal Register notice, or consistent with the licensee's NFPA 805 transition schedule.
The Commission believes that the proposed rule would not achieve its objective. Therefore, the Commission has decided to withdraw the proposed rule.
Dated at Rockville, Maryland this 28th day of February, 2006.
For the Nuclear Regulatory Commission. Annette Vietti-Cook, Secretary of the Commission. [FR Doc. E6-3128 Filed 3-3-06; 8:45 am]
BILLING CODE 7590-01-P
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