ML030920457
| ML030920457 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 01/09/2004 |
| From: | Alexander Adams NRC/NRR/DRIP/RNRP |
| To: | Kuehn G GPU Nuclear Corp |
| ADAMs A, NRC/NRR/DRIP/RNRP, 415-1127 | |
| References | |
| TAC MB5029 | |
| Download: ML030920457 (30) | |
Text
January 9, 2004 Mr. G. A. Kuehn, Jr.
Vice President SNEC and Program Director SNEC Facility GPU Nuclear, Inc.
Route 441 South P.O. Box 480 Middletown, PA 17057-0480
SUBJECT:
SAXTON NUCLEAR EXPERIMENTAL CORPORATION AMENDMENT RE: REMOVAL OF CONTAINMENT VESSEL UPPER DOME (TAC NO. MB5029)
Dear Mr. Kuehn:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 19 to Amended Facility License No. DPR-4 for the Saxton Nuclear Experimental Facility. The amendment consists of changes to the technical specifications (TSs) in response to your application of April 22, 2002, as supplemented on December 5, 2002, and September 30 and December 22, 2003.
The amendment changes the TSs to allow the removal of the containment vessel (CV) upper dome. The amendment also adds the position of Vice-President GPU Nuclear Oversight to the organizational structure.
A copy of the safety evaluation supporting Amendment No. 19 is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Alexander Adams, Jr., Senior Project Manager Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-146
Enclosures:
- 1. Amendment No. 19
- 2. Safety Evaluation cc w/enclosures:
See next page
Saxton Nuclear Docket No. 50-146 Experimental Corporation cc:
Mr. Michael P. Murphy Bureau of Radiation Protection Hopewell Township - Huntingdon County Department of Environmental Protection Supervisors 13th Floor, Rachel Carson State Office ATTN: Reba Fouse, Secretary Building RR 1 Box 95 P.O. Box 8469 James Creek, PA 16657-9512 Harrisburg, PA 17105-8469 Mr. D. Bud McIntyre, Chairman Mr. Jim Tydeman Broad Top Township Supervisors 1402 Wall Street Broad Top Municipal Building Saxton, PA 16678 Defiance, PA 16633 Mr. James H. Elder, Chairman Mr. Don Weaver, Chairman Concerned Citizens for SNEC Safety Liberty Township Supervisors Wall Street Ext. R. D. #1 Saxton, PA 16678 Saxton, PA 16678 Mr. Ernest Fuller U.S. Army Corps of Engineers 1427 Kearney Hill Road Baltimore District Six Mile Run, PA 16679 ATTN: S. Snarski/P. Juhle P.O. Box 1715 Saxton Borough Council Baltimore, MD 21203 ATTN: Judy Burket 707 9th Street The Honorable Robert C. Jubelirer Saxton, PA 16678 President Pro-Temp Senate of Pennsylvania Mr. David J. Thompson, Chair 30th District Bedford County Commissioners State Capitol County Court House Harrisburg, PA 17120 203 South Juliana Street Bedford, PA 15522 Mr. James J. Byrne Three Mile Island Nuclear Generating Mrs. Alexa Cook, Chairman Station Huntingdon County Commissioners P.O. Box 480 County Court House Middletown, PA 17057 Huntingdon, PA 16652 Mr. Robert F. Saunders Saxton Community Library First Energy Corp.
P.O. Box 34 76 South Main Street Saxton, PA 16678 Akron, OH 44308 Carbon Township Supervisors Ms. Mary E. OReilly ATTN: Penny Brode, Secretary First Energy Legal Department R. D. #1, Box 222-C 76 South Main Street Saxton, PA 16678 Akron, OH 44308
Mr. Manuel Delgado 2799 Battlefield Road Fishers Hill, VA 22626 Mr. Eric Blocher 216 Logan Avenue Wyomissing, PA 19610 Mr. David Sokolsky 1000 King Salmon Avenue Eureka, CA 95503 Mr. Gene Baker 501 16th Street Saxton, PA 16678 Mr. Dick Spargo 1004 Main Street Saxton, PA 16678 Mr. Mark E. Warner AmerGen Energy Co., LLC P.O. Box 480 Middletown, PA 17057 Mr. G. A. Kuehn, Jr.
Vice President SNEC and Program Director SNEC Facility GPU Nuclear, Inc.
P.O. Box 480 Middletown, PA 17057-0480 James Fockler, Chairman Dr. William Vernetson Saxton Citizens Task Force Director of Nuclear Facilities 1505 Liberty Street Department of Nuclear Engineering Saxton, PA 16678 Sciences University of Florida Dr. Rodger W. Granlund 202 Nuclear Sciences Center Saxton Independent Inspector Gainesville, FL 32611 Radiation Safety Services 133 Old Main Road Mrs. Bunny Barker State College, PA 16801 Box 143, RR 1 James Creek, PA 16657 Mr. Gareth McGrath Altoona Mirror Mr. Gary Leidich 301 Cayuga Avenue Executive Vice President Altoona, PA 16603 First Energy Nuclear Operating Corp.
76 South Main Street Akron, OH 44308
DHuges PUBLICSee WEresian FGillespie AAdams ccnext w/enclosures:
Enclosures:
page Docket No. 50-146 Issuance A copy organizational will of dome.
the The be safety included amendment The December application structure.
amendment evaluation amendment in Amended the The 22, changes Commissions of2003.
U.S.
Dear supporting April also consists Facility Nuclear the Mr.
adds 22,TSs Kuehn:
2002, License
SUBJECT:
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t DATE ADAMS ACCESSION NO.: ML030920457 DISTRIBUTION:
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- 2. Safety Evaluation
- 1. Amendment No. 19 (TAC RE:NO.
REMOVAL MB5029)
SAXTON OF CONTAIN NUCL RNRP:LA 04/ 03 /03 *EHylton:rdr
- Please see previous concurrence KWitt PIsaac SHolmes JLyons R&TR\RNRP r/f 03/ 10 /03 12/ 23 /03 TechEd
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/RA/
Reactor andSincerely, Adams, and Test Improvement Test Regulation Reactors Jr.,
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1.
E. D. C. B. A. The U.S. Nuclear Regulatory Commission (the Commission) has found statedThis insecurity 10 amendment CFR TheCommission; orissuance Part such tocan the is 51, activities issued be health There and ofconducted Act, this all in and iswill and The amendment applicable accordance reasonable safety stated be the facility Energy without conducted rules December of inrequirements on will the Chapter will assurance with Act the and endangering April be public; not Saxton of in the regulations The possessed 22, compliance 1954, be Iregulations of application 2002, 2003, and inimical that have Title Nuclear as the(i) amended as conforms of 10 in been health the to with the conformity supplemented of of Experimental the for activities the the satisfied.
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(theDPR-4 30 licensee as and fi SAXTON NUCLEAR EXPERIMENTAL AMENDMENT TO AMENDED FACILITY LICENSE DOCKET GPUNO. NUCLEAR, 50-146 INC.
License Amendment No. DPR-4No. 19
Date of
Enclosure:
Issuance: January Appendix 9, A, 2004 Technical 3. 2.
This license amendment is effective (2) Facility indicated as Accordingly, License in the of No. the licen enclosure the DPR-4 date Specifications Changes Specifications.
Nuclear Amendment Theshall Technical possess No. 19, Specifications Technicalthe arefacility herebyincontained incorpora Specifications accorda Office Division New, ofResearch Nuclear Patrick Research of Regulatory Reactor M.
and
/RA/
Madden, and Test Improvement Test Regulation FOR Reactors Chief Reactors THE NUCLEAR Section Programs ProgramREGULATORY COMMISSION indicating pages.
Replace the Theareas the revised following of change.
pages pages are iden of A ENCLOSURE AMENDED FACILIT 20 13 12 11 10 9 6 5 4 3 1 Remove DOCKET NO. 50-146 20 13 12 11 10 9 6 5 4 3 1 Insert
1.0 DEFINITIONS 1.0.1 CONTAINMENT VESSEL -
Term used to describe the vertical steel cylinder which housed the Saxton Nuclear Experimental Corporation Facility Nuclear Steam Supply System (NSSS) and related components, also known as the CV.
1.0.2 Deleted 1.0.3 DECOMMISSIONING ACTIVITIES -
The term DECOMMISSIONING ACTIVITIES describes all of those activities needed to decommission the SNEC Facility and return the site to unrestricted use. Examples of these activities include; PRODUCTION ACTIVITIES needed to conduct decommissioning such as physical dismantlement; radioactive waste preparation, treatment, packaging and shipment; radiation protection activities, construction and installation of support systems, structures and components, and final status survey.
1.0.4 Deleted 1.0.5 Deleted Amendment No. 19 January 9, 2004
1.0.11 PROCESS CONTROL PROGRAM (PCP) -
The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1.0.12 PRODUCTION ACTIVITIES -
PRODUCTION ACTIVITIES include all of the physical activities needed to conduct the decommissioning of the SNEC facility site. Included are such activities as the removal of systems, structures and components, demolition of structures and associated components, removal of contaminants to allow free release, excavation, trenching and removal of underground facilities.
These activities are a sub-set of DECOMMISSIONING ACTIVITIES.
1.0.13 RADIOACTIVE WASTE MANAGEMENT ACTIVITIES -
The term RADIOACTIVE WASTE MANAGEMENT ACTIVITIES is defined as those activities which involve the handling of radioactive waste materials.
1.0.14 Deleted 1.0.15 SITE BOUNDARY -
The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is the line formed by a 200 meter radius from the center of the containment vessel.
Amendment No. 19 January 9, 2004
1.0.16 SNEC -
The term SNEC is an acronym for the Saxton Nuclear Experimental Corporation.
1.0.17 SUBSTANTIVE CHANGE(S) -
SUBSTANTIVE CHANGE(S) are those which affect the activities associated with a document or the documents meaning or intent. Examples of non-substantive changes are: (1) correcting spelling; (2) adding (but not deleting) sign-off spaces; (3) blocking in notes, cautions, etc.; (4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the Technical Specifications; and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.
1.0.18 UNRESTRICTED AREA -
An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
As used here the term is used as it applies to radioactive effluents. The definitions as they apply to 10CFR Parts 20 and 100 still apply.
1.1 SITE 1.1.1 Location The Saxton Nuclear Experimental Corporation (SNEC) facility is on a 1.148 acre tract deeded from the Pennsylvania Electric Company to the SNEC. It is located within the property of the Pennsylvania Electric Company near the Borough of Saxton, Pennsylvania, in Liberty Township, Bedford County, Pennsylvania. The Pennsylvania Electric Company property consists of approximately 150 acres along the Raystown Branch of the Juniata River.
1.1.2 Deleted 1.1.3 Deleted 1.1.3.1 Deleted Amendment No. 19 January 9, 2004
1.1.3.2 Deleted 1.1.3.3 Deleted 2.0 PRINCIPAL ACTIVITIES Activities permitted at the SNEC facility shall include the routine and emergency inspections, maintenance associated with the possession of the SNEC facility, characterization activities and activities delineated in section 1.0.3, DECOMMISSIONING ACTIVITIES, of these Technical Specifications.
2.1 Limiting Conditions for Performing DECOMMISSIONING ACTIVITIES 2.1.1 During activities involving removal of the upper dome of the CV that have the potential to cause a MEASURABLE RELEASE to the environment of airborne radioactivity, appropriate ventilation will be operating in a manner such that the release pathway is via the monitored ventilation system exhaust.
2.1.2 When the ventilation exhaust is in operation, the exhaust monitoring instrumentation will be operated simultaneously. The ventilation system will be shutdown if the exhaust monitoring instrumentation is inoperable.
2.1.3 Verification by analysis that release criteria have been satisfied is required prior to making any batch release of liquid waste process effluent. Effluent release calculations will be made in accordance with the OFFSITE DOSE CALCULATION MANUAL.
3.0 ADMINISTRATIVE CONTROLS 3.1 Organization and Responsibilities GPU NUCLEAR has the responsibility for safely performing DECOMMISSIONING ACTIVITIES. Lines of authority, responsibility and communication are procedurally defined and established. The relationships shall be identified and updated, as appropriate, in organizational charts, departmental functional responsibility and relationship descriptions, job descriptions for key Amendment No. 19 January 9, 2004
personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the SNEC Facility USAR.
3.1.1 The GPU NUCLEAR Cognizant Officer is responsible for and provides full-time dedicated staff for the purpose of conducting all activities safely, effectively and in accordance with corporate policies, applicable laws, regulations, licenses and Technical Specifications (TSs).
3.1.2 The Program Director SNEC Facility is responsible for administration of all SNEC facility functions, for direction of all DECOMMISSIONING ACTIVITIES, and for assuring that the requirements of License No. DPR-4 and these TSs are implemented.
3.1.3 The SNEC Facility Site Supervisor provides on-site management and continuing oversight of PRODUCTION ACTIVITIES.
3.1.4 The Radiation Safety Officer (RSO) is responsible for the conduct and oversight of all SNEC radiation safety activities through implementation of the Radiation Protection Plan. All radiological controls personnel shall have stop work authority in matters relating to or impacting radiation safety.
3.1.5 The Group Radiological Controls Supervisor (GRCS) directly supervises radiation safety activities.
3.1.6 Other GPU Inc. personnel provide SNEC facility management with technical support, project management capabilities and manpower.
3.2 Facility Staffing Requirements:
3.2.1 Deleted 3.2.2 The RSO or a GRCS shall be present on site whenever PRODUCTION ACTIVITIES, maintenance, characterization and/or RADIOACTIVE WASTE MANAGEMENT ACTIVITIES are being performed in Radiologically Controlled Areas (RCAs).
Amendment No. 19 January 9, 2004
3.5.1.10 Records of the review activities performed in accordance with 3.5.1.2 through 3.5.1.7 shall be maintained in accordance with section 3.9.
3.5.2 Independent Safety Review 3.5.2.1 The GPU NUCLEAR Cognizant Officer is responsible for ensuring the independent safety review of the subjects described in section 3.5.2.3.
3.5.2.2 Independent safety review shall be completed by an individual or group not having direct responsibility for the performance of activities under review, but who may be from the same functionally cognizant organization as the individual or group performing the original work.
3.5.2.3 GPU NUCLEAR shall collectively have or have access to the experience and competence required to independently review subjects in the following areas:
- nuclear unit operations
- electrical, mechanical and nuclear engineering
- chemistry and radiochemistry
- metallurgy
- instrumentation and control
- radiological safety
- administrative controls and quality assurance practices
- other appropriate fields such as radioactive waste management.
3.5.2.4 Consultants may be utilized as determined by the GPU NUCLEAR Cognizant Officer to provide expert advice.
3.5.2.5 The following subjects shall be independently reviewed by Independent Safety Reviewers:
3.5.2.5.1 Written safety evaluations of changes in the facility and changes of procedures described in the Safety Analysis Report, and of tests or experiments not described in the Safety Analysis Report, which are completed without prior NRC approval under the provisions of 10 CFR 50.59(c). This review is to verify that such changes, tests or Amendment No. 19
January 9, 2004 experiments did not involve a change to the TS or require NRC approval pursuant to 10 CFR 50.59. Written safety evaluations associated with the direct performance of a change, test or experiment shall be completed prior to the initiation of the activity.
3.5.2.5.2 Proposed changes in procedures, in the facility or tests or experiments, any of which involves a change in the TS or require NRC approval pursuant to 10 CFR 50.59. Matters of this kind shall be reviewed prior to their submittal to the NRC.
3.5.2.5.3 Proposed changes to TS or license amendments shall be reviewed prior to submittal to the NRC for approval.
3.5.2.5.4 Violations, deviations and reportable events which require reporting to the NRC in writing. Such reviews are performed after the fact. Review of events covered under this subsection shall include results of any investigations to prevent or reduce the probability of recurrence of the event.
3.5.2.5.5 Written summaries of audit reports identified in section 3.5.4.
3.5.2.5.6 Any other matter involving the facility which a reviewer deems appropriate for consideration or which is referred to the independent reviewers.
3.5.2.6 The Independent Safety Reviewers shall either have a Bachelors Degree in Engineering or the Physical Sciences and five years professional level experience in the area being reviewed or have nine years of appropriate experience in the field of specialty. An individual performing reviews may possess competence in more than one specialty area. Credit toward experience will be given for advanced degrees on a one-for-one basis up to a maximum of two years.
3.5.2.7 Records of reviews encompassed in section 3.5.2.5 shall be maintained in accordance with section 3.9.
3.5.3 Inspection 3.5.3.1 Facility inspections shall be performed in accordance with approved procedures. The inspection activities shall include:
Amendment No. 19 January 9, 2004
- a. Deleted
- b. Deleted
- c. The station ventilation system effluent particulate monitor channel checks, source checks, channel test and channel calibration shall be performed at a frequency specified in the ODCM.
- d. The ventilation system HEPA Filter will be tested to verify efficiencies in accordance with the requirements of the ODCM.
3.5.4 Audits The audit function is independent of the SNEC facility management. Audits shall be performed by qualified individuals, as a minimum, for those activities designated within the scope of the SNEC facilitys Quality Assurance Program.
Audits are generally conducted biennially, however, frequency is based on the level of activity at the SNEC facility. Audits may also be performed at the request of the GPU NUCLEAR Cognizant Officer or Vice-President GPU Nuclear Oversight. Audits are performed in accordance with approved Quality Assurance Plan procedures. The audit procedures identify areas which may be included in the audit scope. Audit reports shall be forwarded to the GPU NUCLEAR Cognizant Officer and the Vice-President GPU Nuclear Oversight within 60 days of completion of the audit.
3.5.5 TMI-2/SNEC Oversight Committee 3.5.5.1 The TMI-2/SNEC Oversight Committee shall report to the Vice-President GPU Nuclear Oversight. The Committee will consist of at least four members. Membership will be on the recommendation of the Committee Chairman and approval of the Vice-President GPU Nuclear Oversight. Three members shall constitute a quorum.
3.5.5.2 It shall be responsible to provide independent overview and assessment of all matters with radiological safety implications relative to activities at the SNEC facility. The Committee will review proposed License and Technical Specification changes, DECOMMISSIONING ACTIVITIES, special nuclear and radioactive material activities, facility changes, radiological conditions, audit reports and NRC Inspection reports and corrective actions for deficiencies identified.
Amendment No. 19 January 9, 2004
3.5.5.3 Meetings shall be held at least three times per year.
3.5.5.4 Written minutes of all meetings shall be prepared and distributed to the Vice-President GPU Nuclear Oversight and the GPU NUCLEAR Cognizant Officer within 30 days of the meeting date.
3.6 Procedures, Programs and Manuals 3.6.1 Procedures 3.6.1.1 Activities which are designated as within the scope of the SNEC facilitys Quality Assurance Program shall be prescribed by written, reviewed and approved procedures of a type appropriate to the circumstances.
3.6.1.2 Written procedures shall be established, implemented and maintained for the activities listed below:
3.6.1.2.1 Characterization, decommissioning and maintenance activities determined to be within the scope of the QA program.
3.6.1.2.2 Access control, emergency actions (including fire protection program implementation), facility inspections and audits.
3.6.1.2.3 Radiological exposure control, survey activities and radwaste shipping and handling.
3.6.1.2.4 Activities which could result in a MEASURABLE RELEASE to the environment.
3.6.1.3 These procedures shall require that the following actions be taken:
3.6.1.3.1 All DECOMMISSIONING ACTIVITIES and maintenance work under Health Physics control shall be consistent with 10 CFR Part 20 requirements to minimize the radiation exposure of personnel and to prevent the release of radioactivity in excess of allowable limits to the environment.
3.6.1.3.2 All radiation surveys, tests, counting work, radiation exposure control measures and all other work performed in radiologically controlled areas shall conform with the requirements of the Radiation Protection Plan.
Amendment No. 19 January 9, 2004
3.6.1.3.3 Facility inspections shall meet specific requirements of section 3.5.3 of these TS.
3.6.1.4 These procedures and any subsequent revisions shall be prepared, reviewed and approved in accordance with the requirements of the applicable administrative procedure requirements prior to their initial use.
3.6.2 Programs The following programs shall be established, implemented, and maintained during DECOMMISSIONING ACTIVITIES:
3.6.2.1 Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR, Section 50.36(a) for the control of radioactive effluents and for maintaining the doses to MEMBER(S) OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
3.6.2.1.1 Limitations on the OPERABILITY of radioactive effluent monitoring instrumentation, including surveillance tests and setpoint determination in accordance with the methodology in the ODCM; 3.6.2.1.2 Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentrations specified in 10 CFR 20, Parts 20.1001 - 20.2402, Appendix B, Table 2, Column 2; 3.6.2.1.3 Monitoring, sampling, and analysis of radioactive effluents in accordance with 10 CFR, Part 20.1302 and with the methodology and parameters in the ODCM; 3.6.2.1.4 Limitations on the annual and quarterly doses or dose commitment to a MEMBER(S) OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR, Part 50; Amendment No. 19 January 9, 2004
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(DSF) 3.5.3.1.b.
system.
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consists to southeast facilitate ofthe The radioactive Material ofDECOMMISSIONING DECOMMISSIONING three the of decommissioning the structures, material Handling containment DECOMMISSIONINGfor Bay the shipping.
and DECOMMISSIONING vessel SUPPORT SUPPORT process the (CV)
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FACILITY SUPPORT (DSB) preparation Facility.
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handling in dictated entry, be the waste.
completed.
to SNEC Before performed package of the DSF).
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into.
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appropriate is a in the is instrumentation release MEASURABLE involving MEASURABLE inoperable.
the CV/DSB will instrumentation pathway operation, CV/DSB pathway be During ventilation removal The is via the shutdown ventilation ventilation will activities ventilation the RELEASE is exhaust of will is RELEASE via be inoperable.
monitored the be ifsystem upper operated the systemthe operating monitoring to thewithin exhaust monitored exhaust toinwill the ventilation dome athe simultaneously.
be environment of is environment themonitoring CV/DSB in operating ventilation CVoperation, ofthatthatinof havesystem The have athe airborne manner exhaust the exhaust.
potential radioactivity, such that to cause a forIn additional theNRC licensees result reflect staff.
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Nuclear TermandCONTAINMENT Experimental used related to describe components, (NSSS)
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licensees the analyzed for by accidents release.
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reports.
Oversight site.
nature boundary SNEC forwarded to in local issued would consequences GPU nuclear Officer, TMI-2/SNEC over Officer, TS the level Oversight licensees The the Oversight Committee.
One engineering 3.5.5.1 reflects GPU Nuclear and became responsibility add responsibility on Vice-President within has oversight who as who type In to April acceptable the Nuclear TS the been have will as the is currently the currently of Cogniza Oversigh title FirstEne 20, of 3.5.4 added the Vice-P receiv merge merg requ given func Vic 199 Co ma fro toco t
Date:Principal January andregulations, Contributor:
security 9,
proposed 2004 reasonable Theor and staff activities; the published A.was health (3) assurance has Adams, significant the published The concluded, (2) on and issuance Commission Jr.
such 6.0 January safety that hazards CONCLUSION inamendment.
activities the the on of environmental of 22, this the health 10 Federal the consideration, has 2003 Accordingly, CFR basis amendment will public.
changes previously and Portions be (68 51.22(c)(10).
Register ofsafety conducted FR the assessment with inthe environmental 3054).
considerations and will of recordkeeping, issued on of the categorical this amendment not the there January occupational issuance in Pursuant amendment effluents be public acompliance need has proposed involves inimical inspection 7,
exclusion been impact will be discussed of component meets 2003 reporting, to that this prepared Portions radiation not no 10 tono (the finding with may (68 the amendment.
statement significant CFR be the public 5.0 and set addition endangered the common FR above, be eligibility or of located 51.22(b),
in that exposure.
forth ENVIRONMENTAL surveillance proposed Commissions 798),
released administrative this comment connection Inthe or increase in that of accordance amendment defense with within environmental 10 amendment Vice-President criteria no (1) by CFR issuance off Accordingly, on aenvironmen requiremen the there with the correction site, inthe for 51.22(c procedu the restric with the (CV categ and findin isCO of am inv is aN tr