ML003672216

(Duplicate of ML993490086) for Comment Issue of Draft Regulatory Guide DG-1081, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors.

ML003672216
Person / Time
Issue date:	12/31/1999
From:	Office of Nuclear Regulatory Research
To:
References
DG-1081 RG01.X 123199 FC
Download: ML003672216 (58)

Text

R ES-00.

,5R.0,_ U.S. NUCLEAR REGULATORY COMMISSION March 2000 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 Draft DG-1075 DRAFT REGULATORY GUIDE

__Contact: R.L. Sullivan (301)415-1123 DRAFT REGULATORY GUIDE DG-1075 (Proposed Revision 4 to Regulatory Guide 1.101)

EMERGENCY PLANNING AND PREPAREDNE.SS FOR NUCLEAR POWER REACTORS .,,.

A. INTRODUCTION In § 50.47, "Emergency Plans," of 10 CFR Part 50,, ,"Domieb~s.tLicensing of Production and Utilization Facilities," paragraph (a)(1) states that no operain ligicen'se for a nuclear power reactor will be issued unless a finding is made by the NRC th herji'srasonable assurance that adequate protective measures can and will be taken in the ev"ent*I 'a radiological emergency. For operating power reactors, 10 CFR 50.54(s)(2)(ii) requires th[ ". . . the NRC finds that the state.of emergency preparedness does not provide re*b t*,@ assurance that adequate protective measures can and will be taken in the event of a radiolo 0,11. ergency... the Commission will determine

- whether the reactor shall be shut down -h ,ucIMdeficiencies are remedied or whether other enforcement action is appropriate." ln!.oth ,ses,the NRC will base its finding on a review of the Federal Emergency Management nd A) findings and determinations as to whether State and local emergency plans are a quate, anhd capable of being implemented, in addition to the NRC assessment as to whether the Ii31se16 emergency plans are adequate and capable of being implemented.

Onsite and oofA emergency response plans must meet the standards that are listed in 10 CFR 50.47 in oA .rl%,be staff to make a positive finding that there is reasonable assurance that adequat easures can and will be taken in the event of a radiological emergency.

One of theseA .s,10 CFR 50.47(b)(4), pertains to the development of emergency action levels (E , IV, "Content of Emergency Plans," of Appendix E to 10 CFR Part 50 also containg! %ir' :s for the development and review of EALs.

This regulatory guide is being issued in draft form to involve the public in the early stages of the development of a regulatory position in this area.

It has not received complete staff review and does not represent an official NRC staff position.

Public comments are being solicited on the draft guide (including any implementation schedule) and its associated regulatory analysis or value/impact statement. Comments should be accompanied by appropriate supporting data. Written comments may be submitted to the Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Comments may be submitted electronically or downloaded through the NRC's interactive web site at <WWW.NRC.GOV> through Rulemaking. Copies of comments received may be examined at the web site or at the NRC Public Document Room, 2120 L Street NW., Washington, DC. Comments will be most helpful if received by May 22, 2000.

Requests for single copies of draft or active regulatory guides (which may be reproduced) or for placement on an automatic distribution list for

'. single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301)415-2289; or by email to <DISTRIBUTION@NRC.GOV>.

Electronic copies of this draft guide, Accession Number ML003687957, are available in NRC's Public Electronic Reading Room, which can be accessed through NRC's web site, <WWW.NRC.GOV>

VrcD'

This regulatory guide is being developed to provide guidance to licensees and applicants on methods acceptable to the NRC staff for complying with the NRC's regulations for emergency response plans and preparedness at nuclear power reactors. Licensees and applicants may propose means other than those specified by the provisions of the Regulatory Position of this guide for meeting applicable regulations. No new positions or requirements are being imposed by this regulatory guide. Implementation of this guidance by licensees will be on a strictly voluntary basis.

Regulatory guides are issued to describe to the public methods acceptable to the NRC staff for implementing specific parts of the NRC's regulations, to explain techniques used by the staff in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations, and compliance with regulatory guides is not required. Regulatory guides are issued in draft form for public comment to involve the public in developing the regulatory positions. Draft regulatory guides have not received complete staff review; they therefore do not represent official NRC staff positions.

The information collections contained in this draft regulatory guide are covered by the requirements in 10 CFR Part 50, which were approved by the Office of Management and Budget, approval number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.

B. DISCUSSION Revision 1 to NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,"' was published in November 1980 to provide specific acceptance criteria for complying with the standards set forth in 10 CFR 50.47. FEMA, NRC, and other involved Federal agencies intend to use the guidance contained in Revision 1 of NUREG-0654/FEMA REP-i in their individual and joint reviews of the radiological emergency response plans and preparedness of State and local governments and the plans and preparedness of applicants for and holders of a license to operate a nuclear power reactor. Revisions 2 and 3 of Regulatory Guide 1.101 endorsed Revision 1 of NUREG-0654/FEMA-REP-1.

In January 1992, the Nuclear Utilities Management and Resource Council (NUMARC) issued Revision 2 of NUMARC/NESP-007, "Methodology for Development for Emergency Action Levels," 2 which contained guidance on EAL development that accounted for lessons 1

Copies are available at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328 (telephone (202)512-1800); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161; (telephone (703)487-4650;

<http://www.ntis.gov/ordernow>. Copies are available for inspection or copying for a fee from the NRC Public Document Room at 2120 L Street NW., Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202)634-3273 or (800)397-4209; fax (202)634-3343; email is PDR@NRC.GOV.

2 Copies are available for inspection or copying for a fee from the NRC Public Document Room at 2120 L Street NW., Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202)634-3273 or (800)397-4209; fax (202)634-3343; email <PDR@NRC.GOV>.

2

learned from ten years of using the NUREG-0654 guidance. The NRC stated in Revision 3 of Regulatory Guide 1.101 (August 1992), that Revision 2 of NUMARC/NESP-007 was considered to be an acceptable alternative to the guidance provided in NUREG-0654 for development of EALs to comply with 10 CFR 50.47 and Appendix E to 10 CFR Part 50.

In addition, the NRC stated in Revision 3 of Regulatory Guide 1.101 that there is a likelihood that the results of ongoing risk studies related to shutdown may necessitate revision of both the NRC EAL guidance (NUREG-0654) and the NUMARC EAL guidance (NUMARC/NESP 007). Appendix E to 10 CFR Part 50 specifies that EALs are to be used as criteria for determining the need for taking emergency response actions (e.g., notification of emergency response organizations). The need for emergency response actions depends on the degree of degradation of plant safety during an event. The shutdown risk studies have demonstrated that events warranting emergency classification and response (although very unlikely) can occur in the shutdown and refueling mode of plant operation. Therefore, licensees' emergency plans should include EALs which appropriately classify these events in order to meet the requirements in Appendix E to 10 CFR Part 50.

In February 2000, the Nuclear Energy Institute submitted guidance (NEI 99-01, Draft Final Revision 4, February 2000, "Methodology for Development of Emergency Action Levels") 3 for developing EALs applicable in the shutdown and refueling modes of plant operations. NEI 99-01 also provided new guidance for developing EALs for permanently shutdown reactors and dry cask spent fuel storage at nuclear power plants. In addition, improvements to the NUMARC/NESP-007 EAL guidance were incorporated into NEI 99-01; these improvements were first developed (and the rationale behind the revision discussed) in NEI 97-03, Draft Final Revision 3, "Methodology for Development of Emergency Action Levels" (December 1998)). NEI 97-03 was not endorsed by the NRC because the NRC applied its resources to the review of NEI 99-01, which incorporates the guidance in NEI 97-03.

In Revision 3 to Regulatory Guide 1.101, the NRC stated that "Licensees may use either NUREG 0654/FEMA-REP-1 or NUMARC/NESP-007 in developing their EAL scheme but may not use portions of both methodologies." The staff stated in EPPOS No. 1, "Emergency Preparedness Position (EPPOS) on Acceptable Deviations from Appendix 1 of NUREG-0654 Based upon the Staff's Regulatory Analysis of NUMARC/NESP-007,

'Methodology for Development of Emergency Action Levels,"' 4 that it recognizes that licensees who continue to use EALs based upon NUREG-0654 could benefit from the technical basis for EALs provided in NUMARC/NESP-007. However, the staff also recognized that the classification scheme must remain internally consistent. Likewise, licensees can benefit from guidance provided in NEI 99-01 without revising their entire EAL scheme. This is particularly so in regard to adopting guidance on EALs for cold shutdown and refueling modes of operations or for Independent Fuel Storage Facilities. However, the licensee needs to ensure that its EAL scheme remains internally consistent (i.e., the EALs 3Electronic copies (Accession Number ML003689020) are available in NRC's Public Electronic Reading Room, which can be accessed through the NRC's web site, <WWW.NRC.GOV> .

4Copies are available (request Accession Number 9506150406) for inspection or copying for a fee from the NRC Public Document Room at 2120 L Street NW., Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202)634-3273 or (800)397-4209; fax (202)634-3343; email

<PDR@NRC.GOV>.

3

making up the scheme are integrated so as to cover the spectrum of conditions that may warrant classification in a logical manner).

C. REGULATORY POSITION The criteria and recommendations in Revision 1 of NUREG-0654/FEMA-REP-1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" (November 1980), are methods acceptable to the NRC staff for complying with the standards in 10 CFR 50.47 that must be met in onsite and offsite emergency response plans. These criteria provide a basis for NRC licensees and State and local governments to develop acceptable radiological emergency plans and improve emergency preparedness.

The guidance in NUMARC/NESP-007 (Revision 2, January 1992), "Methodology for Development of Emergency Action Levels," is acceptable to the NRC staff as an alternative method to that described in Appendix 1 to NUREG-0654/FEMA-REP-1 for developing EALs required in Section IV.B of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4). In addition, the guidance contained in NEI 99-01 (Draft Final Revision 4, February 2000),

"Methodology for Development of Emergency Action Levels,"' is acceptable to the NRC staff as an alternative method to that described in Appendix 1 to NUREG-0654/FEMA-REP-1 and NUMARC/NESP-007 for developing EALs required in Section IV of Appendix E to 10 CFR Part 50 and 10 CFR 50.47(b)(4).

D. IMPLEMENTATION The purpose of this section is to provide information to licensees and applicants regarding the NRC staff's plans for using this regulatory guide.

This proposed revision has been released to encourage public participation in its development. Except in those cases in which an applicant or licensee proposes an acceptable alternative method for complying with specified portions of the NRC's regulations, the method to be described in the active guide reflecting public comments will be used in the evaluation of emergency plans and preparedness for nuclear power reactors.

4

REGULATORY ANALYSIS A separate Regulatory Analysis was prepared for this proposed Revision 4 to Regulatory Guide 1.101, "Regulatory Analysis for Proposed Revision 4 of Regulatory Guide 1.101 To Accept the Guidance in NEI 99-01 as an Alternative Methodology for the Development of Emergency Action Levels." Electronic copies of the Regulatory Analysis are available in NRC's Public Electronic Reading Room, which can be accessed through the NRC's web site at <WWW.NRC.GOV>, under Accession Number ML003688176.

ADAMS Accession Number of DG-1075 is ML003687957.

5

Federal Recycling Program UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 12 0 55 564215 002 DG1075 US NRC-OCIO 1 1WFN-P -17 DIV INWORMATION MANAGEMENT DESK RMB/DOCUMENT CONTROL WASHINGTON, DC 20555