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10 CFR 50 Appendix E, Appendix E to Part 50-Emergency Planning and Preparedness for Production and Utilization Facilities - kanterella
Appendix E to Part 50-Emergency Planning and Preparedness for Production and Utilization Facilities Table of Contents
<a name="1_appe"></a>I. Introduction
3. The potential radiological hazards to the public associated with the operation of research and test reactors and fuel facilities licensed under 10 CFR parts 50 and 70 involve considerations different than those associated with nuclear power reactors. Consequently, the size of Emergency Planning Zones<a href="#N_1_appe" id="ftn1-50-appe" title="Footnote 1 hyperlink">1</a> (EPZs) for facilities other than power reactors and the degree to which compliance with the requirements of this section and sections II, III, IV, and V of this appendix as necessary will be determined on a case-by-case basis.<a href="#N_2_appe" id="ftn2-50-appe" title="Footnote 2 hyperlink">2</a>
<a name="2_appe"></a>II. The Preliminary Safety Analysis Report
<a name="3_appe"></a>III. The Final Safety Analysis Report; Site Safety Analysis Report
The final safety analysis report or the site safety analysis report for an early site permit that includes complete and integrated emergency plans under § 52.17(b)(2)(ii) of this chapter shall contain the plans for coping with emergencies. The plans shall be an expression of the overall concept of operation; they shall describe the essential elements of advance planning that have been considered and the provisions that have been made to cope with emergency situations. The plans shall incorporate information about the emergency response roles of supporting organizations and offsite agencies. That information shall be sufficient to provide assurance of coordination among the supporting groups and with the licensee. The site safety analysis report for an early site permit which proposes major features must address the relevant provisions of 10 CFR 50.47 and 10 CFR part 50, appendix E, within the scope of emergency preparedness matters addressed in the major features.
<a name="4_appe"></a>IV. Content of Emergency Plans
1. The applicant's emergency plans shall contain, but not necessarily be limited to, information needed to demonstrate compliance with the elements set forth below, i.e., organization for coping with radiological emergencies, assessment actions, activation of emergency organization, notification procedures, emergency facilities and equipment, training, maintaining emergency preparedness, recovery, and onsite protective actions during hostile action. In addition, the emergency response plans submitted by an applicant for a nuclear power reactor operating license under this part, or for an early site permit (as applicable) or combined license under 10 CFR part 52, shall contain information needed to demonstrate compliance with the standards described in § 50.47(b), and they will be evaluated against those standards.
7. By June 23, 2014, identification of, and a description of the assistance expected from, appropriate State, local, and Federal agencies with responsibilities for coping with emergencies, including hostile action at the site. For purposes of this appendix, "hostile action" is defined as an act directed toward a nuclear power plant or its personnel that includes the use of violent force to destroy equipment, take hostages, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, projectiles, vehicles, or other devices used to deliver destructive force.
2. The plan shall describe provisions for the conduct of emergency preparedness exercises as follows: Exercises shall test the adequacy of timing and content of implementing procedures and methods, test emergency equipment and communications networks, test the public alert and notification system, and ensure that emergency organization personnel are familiar with their duties.<a href="#N_3_appe" id="ftn3-50-appe" title="Footnote 3 hyperlink">3</a>
a. A full participation <a href="#N_4_appe" id="ftn4-50-appe" title="Footnote 4 hyperlink">4</a> exercise which tests as much of the licensee, State, and local emergency plans as is reasonably achievable without mandatory public participation shall be conducted for each site at which a power reactor is located. Nuclear power reactor licensees shall submit exercise scenarios under § 50.4 at least 60 days before use in a full participation exercise required by this paragraph 2.a.
(iii) For a combined license issued under part 52 of this chapter, if the applicant currently has an operating reactor at the site, an exercise, either full or partial participation,<a href="#N_5_appe" id="ftn5-50-appe" title="Footnote 5 hyperlink">5</a> shall be conducted for each subsequent reactor constructed on the site. This exercise may be incorporated in the exercise requirements of Sections IV.F.2.b. and c. in this appendix. If FEMA identifies one or more deficiencies in the state of offsite emergency preparedness as the result of this exercise for the new reactor, or if the Commission finds that the state of emergency preparedness does not provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency, the provisions of § 50.54(gg) apply.
c. Offsite plans for each site shall be exercised biennially with full participation by each offsite authority having a role under the radiological response plan. Where the offsite authority has a role under a radiological response plan for more than one site, it shall fully participate in one exercise every two years and shall, at least, partially participate in other offsite plan exercises in this period. If two different licensees each have licensed facilities located either on the same site or on adjacent, contiguous sites, and share most of the elements defining co-located licensees,<a href="#N_6_appe" id="ftn6-50-appe" title="Footnote 6 hyperlink">6</a> then each licensee shall:
<a name="5_appe"></a>V. Implementing Procedures
No less than 180 days before the scheduled issuance of an operating license for a nuclear power reactor or a license to possess nuclear material, or the scheduled date for initial loading of fuel for a combined license under part 52 of this chapter, the applicant’s or licensee's detailed implementing procedures for its emergency plan shall be submitted to the Commission as specified in § 50.4. Licensees who are authorized to operate a nuclear power facility shall submit any changes to the emergency plan or procedures to the Commission, as specified in § 50.4, within 30 days of such changes.
<a name="6_appe"></a>VI. Emergency Response Data System
a. Data points, if resident in the in-plant computer systems, must be transmitted for four selected types of plant conditions: Reactor core and coolant system conditions; reactor containment conditions; radioactivity release rates; and plant meteorological tower data. A separate data feed is required for each reactor unit. While it is recognized that ERDS is not a safety system, it is conceivable that a licensee's ERDS interface could communicate with a safety system. In this case, appropriate isolation devices would be required at these interfaces.<a href="#N_7_appe" id="ftn7-50-appe" title="Footnote 7 hyperlink">7</a>The data points, identified in the following parameters will be transmitted:
c. All link control and data transmission must be established in a format compatible with the NRC receiving system<a href="#N_8_appe" id="ftn8-50-appe" title="Footnote 8 hyperlink">8</a> as configured at the time of licensee implementation.
a. Any hardware and software changes that affect the transmitted data points identified in the ERDS Data Point Library<a href="#N_9_appe" id="ftn9-50-appe" title="Footnote 9 hyperlink">9</a> (site specific data base residing on the ERDS computer) must be submitted to the NRC within 30 days after the changes are completed.
a. Each licensee shall develop and submit an ERDS implementation program plan to the NRC by October 28, 1991. To ensure compatibility with the guidance provided for the ERDS, the ERDS implementation program plan,<a href="#N_10_appe" id="ftn10-50-appe" title="Footnote 10 hyperlink">10</a> must include, but not be limited to, information on the licensee's computer system configuration (i.e., hardware and software), interface, and procedures.
d. Each licensee shall complete implementation of the ERDS by February 13, 1993, or before initial escalation to full power, whichever comes later. Licensees with currently operational ERDS interfaces approved under the voluntary ERDS implementation program<a href="#N_11_appe" id="ftn11-50-appe" title="Footnote 11 hyperlink">11</a> will not be required to submit another implementation plan and will be considered to have met the requirements for ERDS under appendix E to part 50, section VI.1 and 2 of this part.
"[FR" contains a listed "[" character as part of the property label and has therefore been classified as invalid.; 46 FR 28839, May 29, 1981, as amended at 46 FR 63032, Dec. 30, 1981; 47 FR 30236, July 13, 1982; 47 FR 57671, Dec. 28, 1982; 49 FR 27736, July 6, 1984; 51 FR 40310, Nov. 6, 1986; 52 FR 16829, May 6, 1987; 52 FR 42086, Nov. 3, 1987; 56 FR 40185, Aug. 13, 1991; 59 FR 14090, Mar. 25, 1994; 61 FR 30132, June 14, 1996; 70 FR 3599, Jan. 26, 2005; 72 FR 49506, Aug. 28, 2007; 73 FR 42674, Jul. 23, 2008; 76 FR 72596, Nov. 23, 2011; 78 FR 34248, Jun. 7, 2013]
<a href="#ftn1-50-appe" name="N_1_appe" title="Footnote 1">1</a> EPZs for power reactors are discussed in NUREG-0396; EPA 520/1-78-016, "Planning Basis for the Development of State and Local Government Radiological Emergency Response Plans in Support of Light Water Nuclear Power Plants," December 1978. The size of the EPZs for a nuclear power plant shall be determined in relation to local emergency response needs and capabilities as they are affected by such conditions as demography, topography, land characteristics, access routes, and jurisdictional boundaries. The size of the EPZs also may be determined on a case-by-case basis for gascooled nuclear reactors and for reactors with an authorized power level less than 250 MW thermal. Generally, the plume exposure pathway EPZ for nuclear power plants with an authorized power level greater than 250 MW thermal shall consist of an area about 10 miles (16 km) in radius and the ingestion pathway EPZ shall consist of an area about 50 miles (80 km) in radius.
<a href="#ftn2-50-appe" name="N_2_appe" title="Footnote 2">2</a> Regulatory Guide 2.6 will be used as guidance for the acceptability of research and test reactor emergency response plans.
<a href="#ftn3-50-appe" name="N_3_appe" title="Footnote 3">3</a> Use of site specific simulators or computers is acceptable for any exercise.
<a href="#ftn4-50-appe" name="N_4_appe" title="Footnote 4">4</a> Full participation when used in conjunction with emergency preparedness exercises for a particular site means appropriate offsite local and State authorities and licensee personnel physically and actively take part in testing their integrated capability to adequately assess and respond to an accident at a commercial nuclear power plant. Full participation includes testing major observable portions of the onsite and offsite emergency plans and mobilization of State, local and licensee personnel and other resources in sufficient numbers to verify the capability to respond to the accident scenario.
<a href="#ftn5-50-appe" name="N_5_appe" title="Footnote 5">5</a> Partial participation when used in conjunction with emergency preparedness exercises for a particular site means appropriate offsite authorities shall actively take part in the exercise sufficient to test direction and control functions; i.e., (a) protective action decision making related to emergency action levels, and (b) communication capabilities among affected State and local authorities and the licensee.
<a href="#ftn6-50-appe" name="N_6_appe" title="Footnote 6">6</a>Co-located licensees are two different licensees whose licensed facilities are located either on the same site or on adjacent, contiguous sites, and that share most of the following emergency planning and siting elements:
a. Plume exposure and ingestion emergency planning zones; b. Offsite governmental authorities; c. Offsite emergency response organizations; d. Public notification system; and/or e. Emergency facilities.
<a href="#ftn7-50-appe" name="N_7_appe" title="Footnote 7">7</a> See 10 CFR 50.55a(h) Protection Systems.
<a href="#ftn8-50-appe" name="N_8_appe" title="Footnote 8">8</a> Guidance is provided in NUREG-1394, Revision 1.
<a href="#ftn9-50-appe" name="N_9_appe" title="Footnote 9">9</a> See NUREG-1394, Revision 1, appendix C, Data Point Library.
<a href="#ftn10-50-appe" name="N_10_appe" title="Footnote 10">10</a> See NUREG-1394, Revision 1, section 3.
<a href="#ftn11-50-appe" name="N_11_appe" title="Footnote 11">11</a> See NUREG-1394, Revision 1.
NRC website 10 CFR 50 Appendix E
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This page was last edited on 21 October 2016, at 16:44.