NEI 07-08A [Revision 0]

Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures are as Low as is Reasonably Achievable (ALARA)

October 2009

NEI 07-08A [Revision 0]

Nuclear Energy Institute

Generic FSAR Template Guidance for Ensuring that

Occupational Radiation Exposures are as Low as is

Reasonably Achievable (ALARA)

October 2009

NEI 07-08A (Revision 0) October 2009

ACKNOWLEDGEMENTS

This program description document, Generic FSAR Template Guidance For Ensuring That Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA), NEI 07-08A, Revision 0, was developed by the NEI New Plant Radiation Protection and Radioactive Waste Task Force. We appreciate the time, efforts and expertise of the individuals who contributed to the development of this guideline.

NOTICE

Neither NEI, nor any of its employees, members, supporting organizations, contractors, or consultants make any warranty, expressed or implied, or assume any legal responsibility for the accuracy or completeness of, or assume any liability for damages resulting from any use of, any information apparatus, methods, or process disclosed in this report or that such may not infringe privately owned rights.

EXECUTIVE SUMMARY

NEI 07-08A, Revision 0, Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA), provides a complete generic program description for use in developing construction and operating license (COL) applications. The document reflects contemporary Nuclear Regulatory Commission (NRC) guidance, including Regulatory Guide 1.206, “Combined License Applications for Nuclear Power Plants,” and industry-NRC discussions regarding the applicable standard review plan section. A main objective of this program description is to assist in expediting NRC review and issuance of the combined license.

The industry guidance was endorsed by an NRC Final Safety Evaluation (SER) dated October 15, 2009, which is provided as Appendix A. Appendix B also provides NRC Requests for Additional Information.

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TABLE OF CONTENTS

EXECUTIVE SUMMARY ....................................................................................................... i

12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE ALARA ............... 1

12.1.1 OPERATIONAL POLICIES .....................................................................................112.1.2 REGULATORY COMPLIANCE .............................................................................212.1.3 OPERATIONAL CONSIDERATIONS ...................................................................2 12.1.4 REFERENCES ...........................................................................................................5

APPENDIX A – NRC FINAL SAFETY EVALUATION ......................................................... A-1 APPENDIX B – NRC REQUESTS FOR ADDITIONAL INFORMATION ............................... B-1

NEI 07-08A (Revision 0) October 2009

GENERIC FSAR TEMPLATE GUIDANCE FOR ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS

REASONABLY ACHIEVABLE (ALARA)

12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE ALARA

12.1.1 OPERATIONAL POLICIES

Company and station policies are to keep all radiation exposure of personnel within limits defined by 10 CFR 20, Standards for Protection Against Radiation (Reference 12.1-1). Administrative procedures and practices related to maintaining radiation exposure of personnel as low as is reasonable achievable (ALARA) are described in this section.

The ALARA policy is consistent with the guidelines of Regulatory Guide 8.8, Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As is Reasonably Achievable (Reference 12.1-7), and Regulatory Guide 8.10, Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As is Reasonably Achievable (Reference 12.1-9) in establishing, organizing, and operating an effective ALARA program.

To varying extents, all station personnel are responsible for ALARA. Each supervisor is responsible for enforcing the ALARA requirements as described in 10CFR 20.1101. Individual workers are responsible for complying with ALARA requirements, which are presented during initial plant training and reinforced through annual retraining in accordance with the requirements contained in 10 CFR 19.12. The extent of ALARA training provided for each person is at least commensurate with the worker’s job responsibilities and plant areas frequented. The radiation protection training program is maintained and implemented by the training department.

To ensure that personnel comply with established radiological policies, procedures and practices, radiation protection management personnel are charged with the responsibility to promptly advise higher management of any radiologically unsafe practices which exceed their authority to correct. They have the authority to halt any operation which, in their judgment, is radiologically unsafe. Radiation protection technicians are responsible for notifying the operations shift supervision or radiation protection management immediately in order to stop work on any operation deemed to be radiologically unsafe.

12.1.2 REGULATORY COMPLIANCE

As further discussed in FSAR Section 12.5, the station’s ALARA policies and practices are consistent with the applicable regulations in 10 CFR 20 (Reference 12.1-1). Compliance with the guidance found in Regulatory Guides 1.8, 1.206, 8.2, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35, 8.36, 8.38, and the applicable portions of

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NEI 07-08A (Revision 0) October 2009

NUREG-1736 (References 12.1-2 and 12.1-4 through 12.1-19) is discussed in FSAR Section 12.5, Radiation Protection. Compliance with Regulatory Guide 1.8 is further discussed in FSAR Section 13.2, Training. ALARA procedures are established, implemented, maintained and reviewed consistent with the 10 CFR 20.1101 and the quality assurance criteria described in [Reference to appropriate section in Chapter 17 or other document to be provided by COL applicant].

12.1.3 OPERATIONAL CONSIDERATIONS

The ALARA program is based on mature programs in use at other operating commercial nuclear facilities. As such, it inherently incorporates lessons-learned from decades of operating experience. Industry operating experience is regularly reviewed, and applicable lessons-learned are incorporated into plans, procedures, and policies as warranted.

Functional Structure

The functional structure for the ALARA program is described in FSAR Section 12.5.

Organizational Structure

Organizational structure is discussed in FSAR Section 13.1 and/or FSAR Section 17.5. the Quality Assurance Program Description.

Radiation Protection Program

The station has a radiation protection program and an ALARA program which contain the operational ALARA philosophy. These programs, made available to plant personnel, define management's commitment to ALARA and designate those individuals who have the responsibility and authority to implement the ALARA program. FSAR Section 12.5 provides a complete description of the radiation protection program.

Training

ALARA training is described in FSAR Sections 12.5 and 13.2.

Procedures

Procedures are developed and maintained in accordance with FSAR Sections 13.5 and 17.5. During initial preparation, radiation protection personnel review the procedures with potential radiological impact for operations, maintenance, refueling, inservice inspections, and operation of the radwaste system for compliance with ALARA guidelines outlined in the radiation protection program.

ALARA Program Review and Improvement

The ALARA Committee and plant management perform periodic reviews of the radiation program content and implementation. In addition to evaluating the implementation of the

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radiation protection program, these reviews are used to monitor workgroup trends as a means of controlling and reducing personnel exposure. All employees are encouraged to submit suggestions on methods of reducing personnel exposure and improving the ALARA program. Operating procedures are revised, as necessary, to incorporate ALARA lessons-learned from these reviews and suggestions.

Plant Modifications

Modifications to plant equipment and facilities are made where they will substantially reduce exposures at a reasonable cost. Specifications for replacement equipment reflect modifications based on experience gained from using the original equipment. Written procedures direct that all proposed plant modifications are screened for potential adverse radiological impacts. The initial screening review of these proposed modifications is typically performed by engineering personnel. Radiological protection and management personnel perform further review as warranted by level of potential radiological impact.

Work Practices

Radiation protection training, the radiation protection plan, the RWP system, and procedure reviews all help to ensure that radiation exposure of personnel is maintained ALARA. The following examples illustrate the incorporation of ALARA work practices:

� Personnel required to be monitored for radiation exposure in accordance with 10 CFR 20.1502 are assigned appropriate dosimetry to establish exposure history.

� Workers are provided with direct-reading dosimeters on jobs, so that the worker can determine accumulated exposure at any time during a job.

� Dose rate meters are used as needed to identify elevated dose rates. � Pre-job briefs are used to review radiological surveys and to plan work before

personnel enter a radiation area. Written procedures provide guidelines regarding the amount of detail to be included in the pre-job briefings.

� Post-job debriefs are used to ascertain lessons learned. Incorporation of these lessons may result in lower personnel exposure on future jobs. The requirement for post-job debriefings is specified by procedures.

� For work involving high radiation areas, high collective doses, high levels of removable contamination relative to site posting criteria for contamination areas, or known or suspected airborne radioactivity areas:

1. Work is preplanned to minimize personnel exposure as defined in ALARA program procedures

2. Radiation protection personnel provide coverage as required by radiation protection procedures.

� On complex jobs in high radiation areas, dry-run training may be utilized. In some cases, mockups are used to familiarize workers with the operations that they are to perform. These techniques are beneficial to improving worker efficiency and minimizing the amount of time spent in the radiation field.

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� On jobs where general area radiation levels are greater than 1.5 rem/hour or when individual exposure greater than 500 mrem per entry is expected, stay times are considered as further protection against unnecessary exposure.

� As practical, work area entry and exit points are established in areas with low radiation levels. This is done to minimize dose accumulated while changing protective clothing and respiratory equipment. Control points are also established to minimize the spread of removable contamination from the job site.

� As much as practicable, jobs and activities such as reading instruction manuals or maintenance procedures, adjusting tools or jigs, repairing valve internals, and prefabricating components are performed outside radiation areas.

� Individuals working in radiologically controlled areas are trained to be aware of the varying intensities of radiation fields within the general vicinity of their job locations, and are instructed to remain in the areas of lower radiation levels as much as possible, consistent with performing their assigned tasks.

� For high radiation area jobs, maps, postings, and/or detailed instructions are provided to clearly delineate the source of radiation or to alert personnel concerning the location of elevated dose rates. Provided with this information, workers will be cognizant of their immediate radiological environment, and will minimize their stay times in areas of elevated dose rates, thus maintaining exposures ALARA.

� Protective clothing and respiratory equipment prescribed by radiation protection personnel are commensurate with the radiological hazards involved. These requirements cannot be modified without the permission of radiation protection personnel. Consideration is given to the discomfort of workers to minimize the effect of protective efforts on efficiency and the time spent in a radiation area.

� Contamination containments (e.g., glove bags, plastic bottles, tents) and special ventilation systems (e.g., HEPA units) are used where practicable when personnel are working on highly contaminated equipment.

� Special tools or jigs are used on jobs when their use permits the job to be performed more efficiently or prevents errors, thus reducing the time spent in a radiation area.

� Where applicable, special tools are used to increase the distance from the source to the worker, thereby reducing the exposure received.

� Consideration is given to the use of remote monitoring of personnel with various combinations of audio, visual and dose information to reduce exposure of personnel. Direct communications (e.g., radios) may be used to further enhance radiation protection.

� Some systems and components which are subject to buildup of activated corrosion products are equipped with flush connections to reduce hot-spot buildup. Prior to performing maintenance work on these systems or components, consideration is given to flushing and/or chemically decontaminating the system or piece of equipment in order to reduce the crud levels, thereby reducing dose rates which may result in lower personnel exposure.

� Permanent shielding is used, where practicable, to reduce radiation exposure at the work site and in designated "waiting areas" for personnel during periods when they are not actively involved in the work.

� On some jobs, temporary shielding such as lead sheets draped or strapped over a pipe or concrete blocks stacked around a piece of equipment is used. Temporary shielding

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is used only if the estimated total exposure, which includes exposure received during installation and removal, is reduced. Experience with such operations is used in developing guidelines in this area.

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12.1.4 REFERENCES

12.1-1 10 CFR 20, Standards for Protection Against Radiation. 12.1-2 USNRC, “Qualification and Training of Personnel for Nuclear Power Plants,”

Regulatory Guide 1.8, Revision 3, May 2000. 12.1-3 USNRC, “Quality Assurance Program Requirements (Operation)”, Regulatory Guide

1.33, Revision 2, February 1978. 12.1-4 USNRC, “Combined License Applications for Nuclear Power Plants (LWR

Edition)”, Regulatory Guide 1.206, June 2007. 12.1-5 USNRC, “Guide for Administrative Practices in Radiation Monitoring”, Regulatory

Guide 8.2, February 1973. 12.1-6 USNRC, “Instructions for Recording and Reporting Occupational Radiation Dose

Data”, Regulatory Guide 8.7, Revision 2, November 2005. 12.1-7 USNRC, “Information Relevant to Ensuring that Exposures at Nuclear Power

Stations Will Be As Low As Is Reasonably Achievable”, Regulatory Guide 8.8, Revision 3, June 1978.

12.1-8 USNRC, “Acceptable Concepts, Models, Equations, and Assumptions for a Bioassy Program”, Regulatory Guide 8.9, Revision 1, July 1993.

12.1-9 USNRC, “Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable”, Regulatory Guide 8.10, Revision 1-R, September 1975.

12.1-10 USNRC, “Instructions Concerning Prenatal Radiation Exposure”, Regulatory Guide 8.13, Revision 3, June 1999.

12.1-11 USNRC, “Acceptable Programs for Respiratory Protection”, Regulatory Guide 8.15, Revision 1, October 1999.

12.1-12 USNRC, “Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants”, Regulatory Guide 8.27, March 1981.

12.1-13 USNRC, “Audible-Alarm Dosimeters”, Regulatory Guide 8.28, August 1981. 12.1-14 USNRC, “Instructions Concerning Risks from Occupational Radiation Exposure”,

Regulatory Guide 8.29, Revision 1, February 1996. 12.1-15 USNRC, “Monitoring Criteria and Methods to Calculate Occupational Radiation

Doses”, Regulatory Guide 8.34, July 1992. 12.1-16 USNRC, “Planned Special Exposures”, Regulatory Guide 8.35, June 1992. 12.1-17 USNRC, “Radiation Dose to the Embryo/Fetus”, Regulatory Guide 8.36, July 1992. 12.1-18 USNRC, “Control of Access to High and Very High Radiation Areas in Nuclear

Power Plants”, Regulatory Guide 8.38, Revision 1, May 2006. 12.1-19 USNRC, “Consolidated Guidance: 10 CFR Part 20 - Standards for Protection Against

Radiation”, NUREG-1736, October 2001.

NEI 07-08A (Revision 0) October 2009

APPENDIX A – NRC FINAL SAFETY EVALUATION

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October 15, 2009

Mr. Russell J. Bell, Director New Plant Licensing Nuclear Generation Division Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 SUBJECT: FINAL SAFETY EVALUATION FOR NUCLEAR ENERGY INSTITUTE TOPICAL REPORT NEI 07-08, GENERIC FINAL SAFETY ANALYSIS REPORT TEMPLATE GUIDANCE FOR ENSURING THAT OCCUPATIONAL

RADIATION EXPOSURES ARE AS LOW AS REASONABLY ACHIEVABLE, REVISION 3 (PROJECT NO. 689)

Dear Mr. Bell: By letter dated September 10, 2007, the Nuclear Energy Institute (NEI) submitted for U.S. Nuclear Regulatory Commission (NRC) staff review its proposed topical report, NEI 07-08, “Generic Final Safety Analysis Report (FSAR) Template Guidance for Ensuring that Occupational Radiation Exposures are as Low as Reasonably Achievable (ALARA),” Revision 0. The template has undergone subsequent revisions. NEI submitted Revision 3 of the ALARA template by letter dated November 24, 2008. Enclosed is the staff’s safety evaluation (SE) which defines the basis for acceptance of NEI 07-08, Revision 3. The NRC staff finds that for combined license (COL) applications, NEI 07-08, Revision 3, provides an acceptable template for assuring that the ALARA program meets applicable NRC regulations and guidance, provided it is used in conjunction with NEI 07-03A, Revision 0, “Generic FSAR Template Guidance for Radiation Protection Program Description.” Our acceptance applies only to material provided in NEI 07-08, Revision 3. We do not intend to repeat our review of the acceptable material described in NEI 07-08, Revision 3. When NEI 07-08, Revision 3 appears as a reference in COL applications, our review will ensure that the material presented applies to the specific application involved. Licensing requests that deviate from NEI 07-08, Revision 3, will be subject to a plant-specific or site-specific review in accordance with applicable review standards. In accordance with the guidance provided on the NRC website, we request that NEI publish the accepted version of NEI 07-08, Revision 3, within 3 months of receipt of this letter. The accepted version should incorporate this letter and the enclosed SE after the title page. The accepted version should also contain historical review information, including NRC’s requests for additional information and your responses. The accepted versions shall include a "-A" (designating accepted) following the report identification symbol.

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R. Bell -2-

If future changes to the NRC's regulatory requirements affect the acceptability of NEI 07-08, Revision 3 or NEI 07-03A, Revision 0, NEI will be expected to revise NEI 07-08 appropriately, or justify its continued applicability for subsequent referencing. If you have any questions, please contact Sheryl A. Burrows at (301) 415-6086 or via email at Sheryl.Burrows@nrc.gov.

Sincerely, /RA/ William F. Burton, Chief Rulemaking and Guidance Development Branch Division of New Reactor Licensing Office of New Reactors Project No. 689 Enclosure: Safety Evaluation cc w/encl: See next page

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R. Bell -2-

If future changes to the NRC's regulatory requirements affect the acceptability of NEI 07-08, Revision 3 or NEI 07-03A, Revision 0, NEI will be expected to revise NEI 07-08 appropriately, or justify its continued applicability for subsequent referencing. If you have any questions, please contact Sheryl A. Burrows at (301) 415-6086 or via email at Sheryl.Burrows@nrc.gov.

Sincerely, /RA/ William F. Burton, Chief Rulemaking and Guidance Development Branch Division of New Reactor Licensing Office of New Reactors Project No. 689 Enclosure: Safety Evaluation cc w/encl: See next page DISTRIBUTION: PUBIC NRGA R/F SBurrows, NRO RRobinson, NRO SBernal, NRO ERoach, NRO SCoffin, NRO

DHabib, NRO RidsNroDnrl RidsNroDnrlNrga RidsOgcMailCenter RidsNroDcip RidsNroDcipChpb

ADAMS ACCESSION NO.: ML091130034 *See SER dated 03/20/2009, ML090410567 NRO-002 OFFICE PM:DNRL/NRGA LA:DNRL/NRGA BC:DCIP/CHPB OGC BC:DNRL/NRGA NAME SBurrows RRobinson TFrye* MSimon

NLO w/comments WBurton

DATE 04/24/2009 04/24/2009 03/20/2009 10/13/2009 10/15/2009 OFFICIAL RECORD COPY

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DCWG - Combined (All) (Revised 10/07/2009) cc: Mr. Glenn H. Archinoff Director AECL Technologies Division of Compliance & Inspection 481 North Frederick Avenue Bureau of Radiation Control Suite 405 Texas Department of State Health Services Gaithersburg, MD 20877 1100 West 49th Street Austin, TX 78756-3189 Mr. Ray Aycock Field Supervisor Mr. Eugene S. Grecheck U.S. Fish and Wildlife Service Vice President Mississippi Ecological Services Office Nuclear Support Services 6578 Dogwood View Parkway Dominion Energy, Inc. Jackson, MS 39213 5000 Dominion Blvd. Glen Allen, VA 23060 Mr. Richard L. Baker Bechtel Power Corporation Mr. Jay M. Gutierrez 5275 Westview Drive Morgan, Lewis & Bockius, LLP Frederick, MD 21703-8306 1111 Pennsylvania Avenue, NW Washington, DC 20004 Scott Bond Callaway Plant Ms. Sophie Gutner P.O. Box 620 P.O. Box 4646 Fulton, MO 65251 Glen Allen, VA 23058 Ms. Michele Boyd Mr. Brian Hastings Legislative Director Public Utility Commission Energy Program William B. Travis Building Public Citizens Critical Mass Energy P.O. Box 13326 and Environmental Program 1701 Noth Congress Avenue 215 Pennsylvania Avenue, SE Austin, TX 78701-3326 Washington, DC 20003 Mr. Adam C. Heflin Ms. Cindy Brizes Senior Vice President and Chief Nuclear Officer U.S. Department of Energy AmerenUE/Callaway Plant P.O. Box A P.O. Box 620 Aiken, SC 29802 Fulton, MO 65251 Mr. Barton Z. Cowan, Esquire Mr. Ronald Kinney Eckert Seamans Cherin & Mellott, LLC South Carolina DHEC 600 Grant Street, 44th Floor 2600 Bull Street Pittsburgh, PA 15219 Columbia, SC 29201

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Dr. Regis A. Matzie Mr. Tom Sliva Senior Vice President and 7207 IBM Drive Chief Technology Officer Charlotte, NC 28262 Westinghouse Electric Company 20 International Drive Mr. David W. Sutherland Windsor, CT 06095 Chesapeake Bay Field Office U.S. Fish and Wildlife Service Mr. Norris McDonald 177 Admiral Cochrane Drive President Annapolis, MD 21401 AAEA 9903 Caltor Lane Mr. Robert E. Sweeney Ft. Washington, MD 20744 IBEX ESI 4641 Montgomery Avenue Dr. Masanori Onozuka Suite 350 Mitsubishi Nuclear Energy Systems, Inc. Bethesda, MD 20814 2300 Wilson Blvd. Suite 300 Mr. Ed Wallace Arlington, VA 22201-5426 General Manager - Projects PBMR Pty LTD Dr. C. Keith Paulson P. O. Box 9396 Mitsubishi Nuclear Energy Systems, Inc. Centurion 0046 300 Oxford Drive, Suite 301 Republic of South Africa Monroeville, PA 15146 Mr. Gary Wright, Director PBMR Pty. Limited Division of Nuclear Facility Safety Lake Buena Vista Building Illinois Emergency Management Agency 1267 Gordon Hood Avenue 1035 Outer Park Drive PO Box 9396 Springfield, IL 62704 Centurion 0046 Republic of South Africa Charles Peterson Pillsbury, Winthrop, Shaw & Pittman, LLP 2300 "N" Street, NW Washington, DC 20037 Mr. Ernest Reed Living Education Center for Ecology and the Arts P.O. Box 2612 Charlottesville, VA 22902

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Email alsterdis@tva.gov (Andrea Sterdis) amonroe@scana.com (Amy Monroe) APAGLIA@Scana.com (Al Paglia) APH@NEI.org (Adrian Heymer) awc@nei.org (Anne W. Cottingham) bevans@enercon.com (Bob Evans) Bill.Moore@luminant.com (Bill Moore) BrinkmCB@westinghouse.com (Charles Brinkman) brock.degeyter@energyfutureholdings.com (Brock Degeyter) Carellmd@westinghouse.com (Mario D. Carelli) carey.fleming@constellation.com (Carey Fleming) chris.maslak@ge.com (Chris Maslak) ck_paulson@mnes-us.com (Keith Paulson) ckpaulson@aol.com (C.K. Paulson) CumminWE@Westinghouse.com (Edward W. Cummins) cwaltman@roe.com (C. Waltman) david.hinds@ge.com (David Hinds) david.lewis@pillsburylaw.com (David Lewis) DeLaBarreR@state.gov (R. DeLaBarre) DJW@NEI.org (Doug Walters) donald.woodlan@luminant.com (Donald Woodlan) ecullington@earthlink.net (E. Cullington) eddie.grant@excelservices.com (Eddie Grant) erg-xl@cox.net (Eddie R. Grant) frank_quinn@comcast.net (Frank Quinn) Fred.Madden@luminant.com (Fred Madden) garry.miller@pgnmail.com (Garry D. Miller) gcesare@enercon.com (Guy Cesare) gedgar@morganlewis.com (George Edgar) GovePA@BV.com (Patrick Gove) gwcurtis2@tva.gov (G. W. Curtis) gzinke@entergy.com (George Alan Zinke) hickste@earthlink.net (Thomas Hicks) ian.c.rickard@us.westinghouse.com (Ian C. Richard) james.beard@gene.ge.com (James Beard) JCaldwell@luminant.com (Jan Caldwell) Jean.Amundson@luminant.com (Jean Amundson) jeff.simmons@energyfutureholdings.com (Jeff Simmons) jerald.head@ge.com (Jerald G. Head) jgutierrez@morganlewis.com (Jay M. Gutierrez) jim.riccio@wdc.greenpeace.org (James Riccio) jim@ncwarn.org (Jim Warren) jin_chung@mnes-us.com

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JJNesrsta@cpsenergy.com (James J. Nesrsta) joel.Friday@ge.com (Joel Friday) John.Conly@luminant.com (John Conly) John.O'Neill@pillsburylaw.com (John O'Neill) Joseph_Hegner@dom.com (Joseph Hegner) joseph_tapia@mnes-us.com (Joseph Tapia) junichi_uchiyama@mnes-us.com (Junichi Uchiyama) karen@seedcoalition.org (Karen Hadden) kcrogers@aol.com (K. C. Rogers) KSutton@morganlewis.com (Kathryn M. Sutton) kwaugh@impact-net.org (Kenneth O. Waugh) lchandler@morganlewis.com (Lawrence J. Chandler) lois@ieer.org (Lois Chalmers) Marc.Brooks@dhs.gov (Marc Brooks) maria.webb@pillsburylaw.com (Maria Webb) marilyn.kray@exeloncorp.com mark.beaumont@wsms.com (Mark Beaumont) Marvin.Smith@dom.com (Marvin L. Smith) masanori_onozuka@mnes-us.com (Masanori Onozuka) masayuki_kambara@mhi.co.jp (Masayuki Kambara) matias.travieso-diaz@pillsburylaw.com (Matias Travieso-Diaz) maurerbf@westinghouse.com (Brad Maurer) mbowling@numarkassoc.com (Marty Bowling) media@nei.org (Scott Peterson) mgiles@entergy.com (M. Giles) mike.blevins@luminant.com (Mike Blevins) mike_moran@fpl.com (Mike Moran) mlucas3@luminant.com (Mitch Lucas) MSF@nei.org (Marvin Fertel) mwetterhahn@winston.com (M. Wetterhahn) nirsnet@nirs.org (Michael Mariotte) patriciaL.campbell@ge.com (Patricia L. Campbell) paul.gaukler@pillsburylaw.com (Paul Gaukler) Paul@beyondnuclear.org (Paul Gunter) pshastings@duke-energy.com (Peter Hastings) rbird1@luminant.com (Bobby Bird) rclary@scana.com (Ronald Clary) REB@NEI.org (Biff Bradley) Rebecca.Smith-Kevern@nuclear.energy.gov (Rebecca Smith-Kevern) RJB@NEI.org (Russell Bell) RKTemple@cpsenergy.com (R.K. Temple) robert.kitchen@pgnmail.com (Robert H. Kitchen) sandra.sloan@areva.com (Sandra Sloan) SauerB@BV.com (Robert C. Sauer)

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Enclosure

SAFETY EVALUATION

REGARDING THE NUCLEAR ENERGY INSTITUTE

TOPICAL REPORT 07-08

“GENERIC FSAR TEMPLATE GUIDANCE FOR ENSURING THAT OCCUPATIONAL

RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE (ALARA)”

REVISION 3

1.0 BACKGROUND By letter dated November 24, 2008, the Nuclear Energy Institute (NEI) submitted Revision 3 of topical report NEI 07-08, “Generic FSAR Template Guidance for Ensuring that Occupational Radiation Exposures are As Low As Is Reasonably Achievable (ALARA)” for U.S. Nuclear Regulatory Commission (NRC) review and acceptance. The topical report provides a complete generic ALARA program description for use with combined license (COL) applications. NEI 07-08 is to be used in conjunction with NEI 07-03A, “Generic FSAR Template Guidance for Radiation Protection Program Description,” Revision 0. NEI 07-08 is not applicable to the review and issuance of construction permits (CPs) or operating licenses (OLs) described under Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). 2.0 REGULATORY EVALUATION The NRC staff verified that NEI 07-08, Revision 3 complies with the following regulations, regulatory guidance, NUREGs, and industry standards:

• 10 CFR Part 19, “Notices, Instructions and Reports to Workers: Inspections and Investigations.”

• 10 CFR Part 20, “Standards for Protection against Radiation.”

• 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.”

• 10 CFR Part 52, AEarly Site Permits; Standard Design Certifications; and Combined

Licenses for Nuclear Power Plants.”

• Regulatory Guide (RG) 1.8, Revision 3, “Qualification and Training of Personnel for Nuclear Power Plants.”

• RG 1.206, ACombined License Applications for Nuclear Power Plants (LWR Edition).”

• RG 8.2, AGuide for Administrative Practices in Radiation Monitoring.@

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• RG 8.7, Revision 2, AInstructions for Recording and Reporting Occupational Radiation Exposure Data.@

• RG 8.8, Revision 3, AInformation Relevant to Ensuring that Occupational Radiation

Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable.@

• RG 8.9, Revision 1, AAcceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program.@

• RG 8.10, Revision 1-R, AOperating Philosophy for Maintaining Occupational Radiation

Exposures as Low as Is Reasonably Achievable.@

• RG 8.13, Revision 3, AInstruction Concerning Prenatal Radiation Exposure.@

• RG 8.15, Revision 1, AAcceptable Programs for Respiratory Protection.@

• RG 8.27, ARadiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants.@

• RG 8.28, AAudible Alarm Dosimeters.@

• RG 8.29, Revision 1, AInstruction Concerning Risks from Occupational Radiation

Exposure.@

• RG 8.34, Revision 1, AMonitoring Criteria and Methods to Calculate Occupational Radiation Doses.@

• RG 8.35, APlanned Special Exposures.@

• RG 8.36, ARadiation Doses to Embryo/Fetus.@

• RG 8.38, Revision 1, AControl of Access to High and Very High Radiation Areas of

Nuclear Power Plants.@

• NUREG-1736, AConsolidated Guidance: 10 CFR Part 20 C Standards For Protection Against Radiation.@

• NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for

Nuclear Power Plants (SRP), Section 12.1, Revision 3, AAssuring That Occupational Radiation Exposures Are As Low As Is Reasonably Achievable (ALARA).@

• NUREG-0800, SRP, Section 12.3-12.4, Revision 3, ARadiation Protection Design

Features.”

• NUREG-0800, SRP, Section 12.5, Revision 3, AOperational Radiation Protection Program.@

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• NUREG-0800, SRP, Section 13.2.2, Revision 3, ANon-Licensed Plant Staff Training.@

• NEI 06-13A, Revision 2, ATemplate for an Industry Training Program.@

• NEI 07-03A, Revision 0, AGeneric FSAR Template Guidance for Radiation Protection Program Description.”

3.0 TECHNICAL EVALUATION As defined in 10 CFR 20.1003, ALARA (acronym for “as low as is reasonably achievable”), means making every reasonable effort to maintain exposures to radiation as far below the dose limits in this part (Part 20) as is practical consistent with the purpose for which the licensed activity is undertaken, taking into account the state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed materials in the public interest. The staff’s review of NEI 07-08, Revision 3, concentrated on the proposed ALARA program description format, attributes and level of detail. In evaluating the adequacy of the format, attributes and level of detail, the staff followed the guidance of NUREG-0800, SRP Section 12.1, SRP Section 12.3, SRP Section 12.5, and SRP Section 13.2.2. SRP Section 12.1 outlines an operational program for assuring that occupational radiation exposures (ORE) are ALARA for design certification (DC), COL, CP, and OL applicants and provides guidance in four ALARA program areas: policy, design, operational, and radiation protection considerations. SRP Section 12.3-12.4 outlines the review of design features and equipment construction used to assure that ORE are ALARA for DC, COL, CP, and OL applicants and provides guidance in five radiation protection operational design areas: facility design features, shielding, ventilation, area radiation and airborne radioactivity monitoring instrumentation and dose assessment. SRP Section 12.5 outlines the review of the operational radiation protection program used to assure that ORE are ALARA for DC, COL, CP, and OL applicants and provides guidance in five radiation protection operational program areas: organization, equipment, instrumentation, facilities and procedures. SRP Section 13.2.2 outlines the training and requalification program guidance for non-licensed facility staff (including radiation protection staff) for DC, COL, CP, and OL applicants and provides guidance in facility staff training. An NEI 07-08 based ALARA program will be implemented in parallel with the milestones described by NEI 07-03A below. Key aspects of the ALARA program, such as: implementation, organization, facilities, instrumentation and equipment, training, and procedures are implemented by the radiation protection program procedures described in NEI 07-03A.

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Therefore, NEI 07-08 must be implemented in conjunction with NEI 07-03A to provide a complete program to meet the regulatory requirements and guidance documents referenced in this template. NEI 07-03A describes a radiation protection program that will be implemented in stages consistent with the following milestones:

1) Prior to initial receipt of by-product, source, or special nuclear materials the following radiation protection program elements will be in place:

a. Organization – A radiation protection supervisor and at least one (1) radiation

protection technician (RPT) for each operating shift, selected, trained and qualified consistent with the guidance in RG 1.8.

b. Facilities – A facility or facilities to support the receipt, storage and control of

non-exempt radioactive sources in accordance with 10 CFR 20.1801, 20.1802, and 20.1906.

c. Instrumentation and Equipment – Adequate types and quantities of

instrumentation and equipment will be selected, maintained, and used to conduct radiation surveys and monitoring (in accordance with 10 CFR 20.1501, and 20.1502) for the types and levels of radiation anticipated for the non-exempt sources that will be possessed under the license.

d. Procedures – Procedures will be established, implemented and maintained

sufficient to maintain adequate control over the receipt, storage and use of radioactive materials that will be possessed under the license and to assure compliance with 10 CFR 19.11 and 19.12 and 10 CFR Part 20.

e. Training – Initial and periodic training will be provided to individuals responsible

for the receipt, control or use of non-exempt radioactive sources possessed under the license in accordance with 10 CFR 19.12 and consistent with the guidance in RGs 1.8, 8.13, 8.27, and 8.29.

2) Prior to receiving reactor fuel under this license, and thereafter, whenever reactor fuel is

possessed under the license, radiation monitoring will be established, implemented and maintained and procedures on criticality accident requirements will be established, implemented and maintained in accordance with 10 CFR 50.68, in addition, to the radiation protection elements specified in item 1 above.

3) Prior to initial loading of fuel in the reactor, all functional program areas described in this

template [NEI 07-03A] will be fully implemented, with the exception of the program elements described in item 4 below. In addition, the position of radiation protection manager (RPM) (as described in Section 12.5.2.3 of NEI 07-03A) will be filled and at least one (1) RPT for each operating shift, who has been selected, trained and qualified consistent with the guidance in RG 1.8, will be onsite and on duty when fuel is initially loaded in the reactor, and thereafter, whenever fuel is in the reactor.

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4) Prior to initial transfer, transport or disposal of radioactive materials, the organization, facilities, equipment, instrumentation, and procedures will be in place as necessary to assure compliance with 10 CFR Part 20, Subpart K, and applicable requirements in 10 CFR Part 71.

3.1 NEI -07-08 TEMPLATE OVERVIEW NEI 07-08 provides guidance for establishing a complete generic ALARA program description for use in developing COL applications. The NEI 07-08 ALARA program shall be used in conjunction with the operational radiation protection program established under the guidance of NEI 07-03A. It will be incumbent on the applicant to provide site specific information, as described in NEI 07-03A, to provide a complete description of an operational radiation protection program which includes the written ALARA administrative policies, procedures and practices, the purpose of which will be to maintain occupational and public doses below regulatory limits and as low as reasonably achievable. Applicants must establish adequate facilities, purchase necessary equipment, and develop site procedures to effectively implement the ALARA program. NEI 07-08 is organized into three areas, Operational Policies, Regulatory Compliance, and Operational Considerations. 3.1.1 OPERATIONAL POLICIES The “Operational Policies” section of NEI 07-08 states that the Company and station policies will keep all radiation exposure of personnel within the limits of 10 CFR Part 20. Additionally, the applicant will establish administrative practices and procedures to organize, implement, and operate an effective ALARA program with an ALARA policy consistent with the guidance of RG 8.8, “Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable,” and RG 8.10, AOperational Philosophy for Maintaining Occupational Radiation Exposures as Low as Is Reasonably Achievable.@ NEI 07-08 further states that all station personnel are responsible for ALARA, and each supervisor is responsible for enforcing the ALARA requirements as described in 10 CFR 20.1101. Training and annual retraining is provided in accordance with the requirements in 10 CFR 19.12. The extent of ALARA training is commensurate with each worker’s responsibilities and work locations. The responsibility for the maintenance and implementation of the radiation protection training program is held by the training department. The staff evaluation considers the training of workers is essential to the ALARA concept. Radiation protection personnel have stop work authority for any operation deemed to be radiologically unsafe. Radiation Protection Management is responsible to promptly notify higher management if the unsafe practices exceed their authority to correct. The staff considers this aspect important to ensuring adequate protection of the worker when radiological conditions are not as anticipated.

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3.1.2 REGULATORY COMPLIANCE The “Regulatory Compliance" section of NEI 07-08 states that the ALARA policies and practices are consistent with the applicable requirements of 10 CFR Part 20 “Standards for Protection against Radiation,@ and the following RGs: 1.8, 1.206, 8.2, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35, 8.36, and 8.38. Additionally, the COL applicant will describe in Final Safety Analysis Report (FSAR) Section 12.5 compliance with NUREG-1736, Consolidated Guidance: 10 CFR Part 20 “Standards for Protection against Radiation,@ and in FSAR Section 13.2, “Training,” compliance with RG 1.8. ALARA procedures will be established, implemented, maintained and reviewed consistent with 10 CFR 20.1101 and the sites’ specific quality assurance criteria (described in FSAR Chapter 17 or other documented COL commitment). 3.1.3 OPERATIONAL CONSIDERATIONS The “Operational Considerations” section of NEI 07-08 outlined below states that based on the mature nature of the ALARA programs in use at other operating commercial nuclear facilities, the industry regularly reviews and incorporates lessons-learned from decades of operating experience. This section is broken down into several areas to provide a description of the features of a standard ALARA program. Under the heading, “Work Practices,” illustrative examples of ALARA tools or processes are described. � Functional Structure

The functional structure of the ALARA program is as described in COL FSAR Section 12.5 (additional details provided in NEI 07-03A).

� Organizational Structure

The organizational structure is as described in COL FSAR Section 13.1 and/or 17.5 (additional details provided in NEI 07-03A).

� Radiation Protection Program

The operational radiation protection program with the ALARA program and the operational ALARA philosophy is as described in COL FSAR Section 12.5 (additional details provided in NEI 07-03A).

� Training The ALARA training program is as described in COL FSAR Section 12.5 (NEI 07-03A) and Section 13.2 (additional details provided in NEI 06-13A). � Procedures The procedures program is as described in COL FSAR Section 13.5 and/or 17.5.

During initial procedure development radiation protection personnel will review the procedures with potential radiological impact for operations, maintenance, refueling, inservice inspection, and radioactive waste operations for compliance with ALARA guidelines (additional details provided in NEI 07-03A).

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� ALARA Program Review and Improvement This subsection describes the functional purpose of the ALARA committee

and plant management reviews of the radiation protection program content and implementation to incorporate lessons learned and ALARA suggestions (additional details provided in NEI 07-03A).

� Plant Modifications This subsection describes the general process to review plant modifications for

adverse ALARA impact (additional details provided in NEI 07-03A). � Work Practices This subsection describes illustrative examples of ALARA tools, good practices,

or processes that are to be used to provide an approach to various levels of radiological risk (such as high collective dose) encountered when performing maintenance, operations, or refueling activities (additional details provided in NEI 07-03A).

3.2 STAFF EVALUATION 3.2.1 POLICY CONSIDERATIONS The objectives of the radiation protection ALARA program are to provide reasonable assurance that the limits of 10 CFR 20.1201, 10 CFR 20.1202, 10 CFR 20.1203, 10 CFR 20.1204, 10 CFR 20.1207, and 10 CFR 20.1208 will not be exceeded; and to ensure that individual ORE are maintained as far below regulatory limits as is reasonably achievable and that total person-rem doses are ALARA, in accordance with the requirements of 10 CFR 20.1003 (ALARA Definition) and the guidelines of RGs 8.8 and 8.10. An NEI 07-08 based ALARA program meets 10 CFR 20.1101 and the definition of ALARA in 10 CFR 20.1003, as they relate to those measures that ensure that radiation exposures to occupational workers and members of the public resulting from licensed activities are below specified limits and ALARA. NEI 07-08 describes that a written ALARA policy will be established in accordance with the requirements in 10 CFR 19.12 and the ALARA provisions of 10 CFR 20.1101(b), and that the policy will be described, displayed, and will be implemented in accordance with the provisions of RGs 8.8 (Regulatory Position C.1) and 8.10 (Regulatory Position C.1) and NUREG-1736, as it relates to maintaining doses ALARA. A specific individual(s) will be designated and assigned responsibility and authority for implementing ALARA policy. NEI 07-08 also states that radiation protection personnel have the responsibility to stop work and immediately notify radiation protection management and operations management, if unsafe radiological practices are noted. Radiation protection management is responsible to advise higher management of unsafe practices that they lack the authority to correct. These programmatic aspects of the ALARA policy are addressed as follows in NEI 07-03A.

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As stated in NEI 07-03A, plant management will issue written policy on radiation protection, consistent with RGs 8.8 and 8.10, which will include the following commitments:

• The design, construction and operation of the plant will be such that occupational and public radiation exposures and releases of licensed radioactive materials will be maintained ALARA.

• Regulatory radiation requirements, dose limits, and limits on releases of radioactive

materials will be complied with.

• A radiation protection program will be implemented and maintained such that radiation doses will be kept below regulatory limits, as well as ALARA.

• Each manager and supervisor in the plant organization will understand and be held

accountable for implementing his or her responsibility to integrate radiation protection controls into work activities.

• Each individual working at the facility will understand and accept the responsibility of

following radiation protection procedures and instructions provided by radiation protection staff and of maintaining his or her dose ALARA.

• The RPM will be provided with the delegable authority to stop work or order an area

evacuated when the radiation conditions warrant such an action and such actions are consistent with plant safety.

• A direct reporting chain will be established from the RPM to the Plant Manager that is

independent of the reporting chains for Operations and Maintenance. • An ALARA committee will be established with delegated authority from the Plant

Manager which will include, at a minimum, the managers of Operations, Maintenance, Work Control, Engineering and Radiation Protection to help assure effective implementation of line organization responsibilities for maintaining worker doses ALARA.

NEI 07-03A also provides additional detail on the RPM (or equivalent), who will report directly to the Plant Manager, independent of the reporting chains for Operations and Maintenance. The duties of the plant RPM will be in accordance with the guidance in RGs 8.8 and 8.10. The radiation protection organization personnel qualifications, personnel training, program objectives, and implementation methods will be in accordance with the guidance contained in RGs 1.8, 8.2, 8.8, 8.10, and 8.13 and will comply with 10 CFR 19.12. An NEI 07-08 based ALARA program meets 10 CFR 19.12, as it relates to keeping workers who receive ORE informed as to the storage, transfer, or use of radioactive materials or radiation in such areas, and instructed as to the risk associated with ORE, precautions and procedures to reduce exposures, and the purpose and function of protective devices employed. Equipment to be used for radiation protection purposes includes portable radiation survey instruments, personnel monitoring equipment, portable area and airborne radioactivity monitors, laboratory equipment, air samplers, respiratory protective equipment, and protective clothing.

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NEI 06-13A, “Template for an Industry Training Program Description,@ Revision 2, (Reference 5.4) describes an acceptable program for training of non-licensed plant staff for COL applicants. Section 1.3 of this template describes radiation worker and plant access training details. Personnel whose job duties require unescorted access to radiological controlled areas of the plant will receive instruction in the applicable aspects of radiation protection. Radiation Worker Training will include the topic, “Concept of as Low as Is Reasonably Achievable (ALARA).” The staff has reviewed the proposed NEI 07-08 and found that when used in conjunction with NEI 07-03A, Revision 0, AGeneric FSAR Template Guidance for Radiation Protection Program Description,” it is acceptable in describing the operational policies of an ALARA program. 3.2.2 REGULATORY COMPLIANCE As described in NEI 07-08, Section 12.1.2, and when used in conjunction with NEI 07-03A, the ALARA policies and practices are consistent with the applicable requirements of 10 CFR Part 20, “Standards for Protection against Radiation,@ and the following RGs: 1.8, 1.206, 8.2, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35, 8.36, and 8.38. Additionally, NEI 07-08 will require the COL applicant to describe in FSAR Section 12.5 compliance with NUREG-1736, Consolidated Guidance: 10 CFR Part 20, “Standards for Protection against Radiation,@ and in FSAR Section 13.2, “Training,” compliance with RG 1.8. As described in NEI 07-08, ALARA procedures will be established, implemented, maintained and reviewed consistent with 10 CFR 20.1101 and the sites’ specific quality assurance criteria (described in FSAR Chapter 17 or other documented COL commitment). The staff has reviewed the proposed NEI 07-08 and found that when used in conjunction with NEI 07-03A, Revision 0, AGeneric FSAR Template Guidance for Radiation Protection Program Description,” it is acceptable in that NEI 07-08 describes the necessary regulatory documents containing the key aspects of an ALARA program for a light water reactor. 3.2.3 DESIGN CONSIDERATIONS As described in NEI 07-08, Section 12.1.3, “Operational Considerations,” the design methods, approach, and interactions for Plant Modifications and ALARA Program Review and Improvement are in accordance with the ALARA provisions of 10 CFR 20.1101(b) and RG 8.8 (Regulatory Position C.2). RG 8.8 includes incorporation of measures for reducing the need for time spent in radiation areas; maintenance; measures to improve the accessibility to components requiring periodic maintenance or ISI; measures to reduce the production, distribution, and retention of activated corrosion products throughout the primary system; measures for assuring that ORE during decommissioning will be ALARA; reviews of the design by competent radiation protection personnel; instructions to designers and engineers regarding ALARA design; experience from operating plants and past designs; and continuing facility design reviews. NEI 07-03A also describes the radiation protection program commitment for 10 CFR 20.1101, as it relates to (a) development, documentation, and implementation of a radiation protection

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program, (b) the use of procedures and controls to achieve doses to workers and the public that are ALARA, as defined in 10 CFR 20.1003, and (c) the review and audit of the radiation protection program content and implementation. The staff has reviewed the proposed NEI 07-08 and found that when used in conjunction with NEI 07-03A, Revision 0, AGeneric FSAR Template Guidance for Radiation Protection Program Description,” it is acceptable in that NEI 07-08 describes the design considerations to consider when implementing an ALARA program for a light water reactor. 3.2.4 OPERATIONAL AND RADIATION PROTECTION CONSIDERATIONS Acceptability is based on evidence that the applicant has a program to develop plans and procedures in accordance with RGs 1.8, 8.8, and 8.10 that can incorporate the experiences obtained from facility operation into facility and equipment design and operations planning and that will implement specific exposure control techniques as discussed in Section 12.1.3 of the NEI 07-08 template. Acceptability is based on evidence as described in NEI 07-03A and NEI 07-08 that overall facility operations, as well as the radiation protection program, integrate the procedures necessary to ensure that radiation doses are ALARA, including work scheduling, work planning, design modifications, and radiological considerations. Under the subsection 12.1.3, “Work Practices,” the applicant describes examples of the current operating nuclear power plants ALARA program work practices, such as remote monitoring via audio and visual means, temporary shielding, work permits (RWPs), and pre-planning (including dry run training or use of mock-ups), which, when used can result in a substantial reduction in ORE. As described in NEI 07-03A, access controls to high and very high radiation areas, when maintained in accordance with 10 CFR 20.1601 and 10 CFR 20.1602, can contribute to better awareness of the hazards to be encountered. Work is to be pre-planned in these areas. The staff reviewed the sections of templates NEI 07-08 (Section 12.1.3)and NEI 07-03A (Section 12.5.4) describing maintenance, repair, surveillance, and refueling procedures and methods to ensure that all plant radiation protection procedures, practices, and criteria have been considered, and that ORE will be ALARA and in accordance with RG 8.8. NEI 07-03A states that ALARA procedures will be established, implemented and reviewed under an ongoing quality assurance program consistent with the requirements of 10 CFR 20.1101. Based on the above review, the staff finds that the proposed NEI 07-08, when used in conjunction with NEI 07-03A, is acceptable in describing the ALARA policies and program. 4.0 CONCLUSION Health Physics Branch (CHPB) staff used the acceptance criteria of SRP Section 12.1 as the main basis for evaluating the acceptability of NEI 07-08. The CHPB staff has determined that NEI 07-08, Revision 3, is consistent with the regulatory requirements, guidance, and industry standards for operational radiation protection programs as outlined in Section 2.0 of this evaluation, with implementation in accordance with the four (4) NEI 07-03A, Revision 0, milestones described in Section 3.0 of this evaluation, and verification of the implementation of the operational program.

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On the basis of it’s review, the staff concludes that NEI 07-08, AGeneric FSAR Template Guidance for Ensuring That Occupational Radiation Exposures are as Low as is Reasonably Achievable (ALARA),@ Revision 3, sufficiently describes the policy elements and operational objectives to enable a reasonable assurance finding of acceptability for issuance of a COL, followed with verification of the implementation of a site and plant-specific operational radiation protection program through the inspection process prior to fuel load. The staff further concludes that NEI 07-08 is adequate and may be referenced in a COL application, and that the implementation of a plant and site-specific operational ALARA program will be executed by COL holders in accordance with the milestones described in COL FSAR Section 13.4 and license conditions. Accordingly, the NEI 07-08 Template, in conjunction with the NEI 07-03A Template, fulfills a licensing requirement for submission of a COL application. A license condition will specify the timing for the licensee to make elements of the site and plant-specific operational radiation protection program available for NRC inspection and verification prior to fuel load. Finally, under the requirements of SECY 05-0197, the implementation of operational programs identified in the NEI 07-08 Template does not necessitate inspection, test, analysis, and acceptance criteria in a DC or COL application. Based on the staff’s review of NEI 07-08 outlined above, the staff concludes that NEI 07-08 clearly and sufficiently describes, in terms of scope and level of detail, plant management written policy on ALARA, when used in conjunction with NEI 07-03A, AGeneric FSAR Template Guidance for Radiation Protection Program Description,” Revision 0, to enable a reasonable assurance finding of acceptability for issuance of a COL with verification of the operational ALARA policy and program during the construction stage. 5.0 REFERENCES 5.1 Nuclear Energy Institute (NEI), NEI 07-03A, AGeneric FSAR Template Guidance for

Radiation Protection Program Description," Revision 0. 5.2 NUREG-0800, SRP, Section 12.5, AOperational Radiation Protection Program,@

March 2007.

5.3 RG 1.206, “Combined License Applications for Nuclear Power Plants, (LWR Edition)” Section C.I.12, “Radiation Protection,” June 2007.

5.4 NEI 06-13A, ATemplate for an Industry Training Program Description," Revision 2,

March 6, 2009.

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NEI 07-08A (Revision 0) October 2009

APPENDIX B – NRC REQUESTS FOR ADDITIONAL INFORMATION

B-1

NEI 07-08A (Revision 0) October 2009

B-2

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am (P

CP)

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crip

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by

the

end

of

Oct

ober

, 200

8, a

nd a

safe

ty e

valu

atio

n fo

r NEI

07-

08,

ALA

RA

, by

late

Nov

embe

r.

Nov

embe

r 200

8 M

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3803

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ric F

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pla

te G

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r

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su

rin

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ow

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s R

ea

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na

bly

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ch

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ble

(A

LA

RA

)

NEI

07-

08 R

ev 3

R

esol

ved

all

com

men

ts a

nd

RA

I’s

Dec

embe

r 11,

200

8 M

L0

83

51

00

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U

pdat

e of

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Tem

plat

e St

atus

N

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AR

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are

co

mp

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for

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07-

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B-4