ML052200028
| ML052200028 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/12/2005 |
| From: | Macon W NRC/NRR/DLPM/LPD3 |
| To: | Bezilla M FirstEnergy Nuclear Operating Co |
| Macon, WA, NRR/DLPM/LPD III-2, 415-3965 | |
| Shared Package | |
| ML052200035 | List: |
| References | |
| TAC MC5473 | |
| Download: ML052200028 (14) | |
Text
September 12, 2005 Mr. Mark B. Bezilla Vice President-Nuclear, Davis-Besse FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: REFUELING OPERATIONS - INSTRUMENTATION (TAC NO. MC5473)
Dear Mr. Bezilla:
The Commission has issued the enclosed Amendment No. 269 to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit 1. The amendment revises the Technical Specifications (TSs) in response to your application dated December 20, 2004, as supplemented by letter dated April 6, 2005.
This amendment revises TS 3/4.9.2, "Refueling Operations - Instrumentation." Specifically, the changes revise TS 3/4.9.2 concerning source range flux monitors to be more consistent with improved Standard Technical Specifications.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
- 1. Amendment No. 269 to NPF-3
- 2. Safety Evaluation cc w/encls: See next page
September 12, 2005 Mr. Mark B. Bezilla Vice President-Nuclear, Davis-Besse FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: REFUELING OPERATIONS - INSTRUMENTATION (TAC NO. MC5473)
Dear Mr. Bezilla:
The Commission has issued the enclosed Amendment No. 269 to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station, Unit 1. The amendment revises the Technical Specifications (TSs) in response to your application dated December 20, 2004, as supplemented by letter dated April 6, 2005.
This amendment revises TS 3/4.9.2, "Refueling Operations - Instrumentation." Specifically, the changes revise TS 3/4.9.2 concerning source range flux monitors to be more consistent with improved Standard Technical Specifications.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
- 1. Amendment No. 269 to NPF-3
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDIII-2 R/F WMacon TBoyce OGC GGrant, RIII ACRS GHill (2)
DClarke GSuh DLPMDPR HNieh Package Accession Number: ML052200035 Amendment Accession Number: ML05220028 TS Accession Number: ML052590015 OFFICE PM:PDIII-2 LA:PDIII-1 SC:SRXB-B SC:IROB-A OGC SC:PDIII-2 NAME WMacon PCoates JNakoski CHarbuck for TBoyce NWilderman GSuh DATE 8/11/05 8/11/05 8/15/05 8/12/05 8/23/05 9/8/05
OFFICIAL RECORD COPY
Davis-Besse Nuclear Power Station, Unit 1 cc:
Mary E. O'Reilly FirstEnergy Corporation 76 South Main St.
Akron, OH 44308 Manager - Regulatory Affairs FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State - Route 2 Oak Harbor, OH 43449-9760 Director, Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, OH 43068-9009 Regional Administrator U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60523-4351 Michael A. Schoppman Framatome ANP 24 Calabash Court Rockville, MD 20850 Resident Inspector U.S. Nuclear Regulatory Commission 5503 North State Route 2 Oak Harbor, OH 43449-9760 Barry Allen, Plant Manager FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State - Route 2 Oak Harbor, OH 43449-9760 Dennis Clum Radiological Assistance Section Supervisor Bureau of Radiation Protection Ohio Department of Health P.O. Box 118 Columbus, OH 43266-0118 Carol OClaire, Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin Granville Road Columbus, OH 43235-2206 Zack A. Clayton DERR Ohio Environmental Protection Agency P.O. Box 1049 Columbus, OH 43266-0149 State of Ohio Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573 Attorney General Office of Attorney General 30 East Broad Street Columbus, OH 43216 President, Board of County Commissioners of Ottawa County Port Clinton, OH 43252 President, Board of County Commissioners of Lucas County One Government Center, Suite 800 Toledo, OH 43604-6506 The Honorable Dennis J. Kucinich United States House of Representatives Washington, D.C. 20515 The Honorable Dennis J. Kucinich United States House of Representatives 14400 Detroit Avenue Lakewood, OH 44107 Mr. Lew W. Myers Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 269 License No. NPF-3 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the FirstEnergy Nuclear Operating Company (the licensee) dated December 20, 2004, as supplemented by letter dated April 6, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 269, are hereby incorporated in the license. FirstEnergy Nuclear Operating Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 12, 2005
ATTACHMENT TO LICENSE AMENDMENT NO. 269 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3/4 9-2 3/4 9-2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 269 TO FACILITY OPERATING LICENSE NO. NPF-3 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-346
1.0 INTRODUCTION
By application to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated December 20, 2004 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML043580232), as supplemented by letter dated April 6, 2005 (ADAMS Accession No. ML050980109), FirstEnergy Nuclear Operating Company (the licensee) requested changes to the Technical Specifications (TSs) for the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The supplement dated April 6, 2005, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 15, 2005 (70 FR 7765).
The proposed changes would revise TS 3/4.9.2, "Refueling Operations - Instrumentation."
Specifically, the proposed changes would revise TS 3/4.9.2 concerning source range flux monitors to be more consistent with improved Standard Technical Specifications (STSs). The proposed TS changes would achieve consistency with corresponding requirements in NUREG-1430, "Standard Technical Specifications Babcock and Wilcox Plants," Revision 3, dated June 2004, with exceptions to account for plant-specific design differences and retention of current licensing basis requirements and commitments.
In this safety evaluation (SE), the NRC staff refers to the current DBNPS TS as a CTS; a standard TS contained in NUREG-1430 as an STS; and the proposed DBNPS TS, which results from changes addressed in this SE, as a PTS. In addition to the requirements and considerations contained in NUREG-1430, the NRC staff based its evaluation of the PTS changes on the Commissions "Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors" (Final Policy Statement), published on July 22, 1993 (58 FR 39132), and Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.36, "Technical specifications," as amended July 29, 1996 (61 FR 39299).
Consistent with the Final Policy Statement, the licensee proposed transferring some CTS requirements to licensee-controlled documents, such as the TS Bases, for which changes are controlled by a regulation such as 10 CFR 50.59, "Changes, tests, and experiments."
Accordingly, if 10 CFR 50.59 does not require prior NRC approval, such transferred requirements may be changed by the licensee without it. However, NRC-controlled documents, such as TSs, may not be changed by the licensee without prior NRC approval. In addition, the licensee emphasized that the PTSs were requested to more closely match the improved STSs.
During its review, the NRC staff relied on the Final Policy Statement, 10 CFR 50.36, the STSs, and DBNPS TSs as guidance for accepting proposed CTS changes. This SE provides a summary basis for the NRC staffs conclusion that the licensee has developed the PTSs based on the STSs and CTSs, except for plant-specific considerations, and that the use of the PTSs are acceptable for continued operation of DBNPS. This SE also explains the NRC staffs conclusion that the PTSs are consistent with the DBNPS current licensing basis and conform to 10 CFR 50.36. In this SE, NRC staff conclusions regarding the conformance and consistency of the PTSs with these requirements are limited to specifications in the CTSs related to the specific changes proposed by the licensee in the subject application, as supplemented. The NRC staff also acknowledges that it is acceptable for the PTSs to differ from the STSs and DBNPS TSs to retain CTS provisions, that are based on the current licensing basis for DBNPS, which the NRC staff has previously reviewed and approved.
For the reasons stated in this SE, the NRC staff finds that the PTSs issued with this license amendment comply with Section 182a. of the Atomic Energy Act (the Act), as amended, 10 CFR 50.36, and the guidance in the Final Policy Statement, and that they are in accordance with the common defense and security and provide adequate protection of the health and safety of the public.
2.0 REGULATORY EVALUATION
Section 182a. of the Act requires that applicants for nuclear power plant operating licenses will state:
[S]uch technical specifications, including information of the amount, kind, and source of special nuclear material required, the place of the use, the specific characteristics of the facility, and such other information as the Commission may, by rule or regulation, deem necessary in order to enable it to find that the utilization... of special nuclear material will be in accord with the common defense and security and will provide adequate protection to the health and safety of the public. Such technical specifications shall be a part of any license issued.
In 10 CFR 50.36, the Commission established its regulatory requirements related to the content of TSs. In doing so, the Commission placed emphasis on those matters related to the prevention of accidents and the mitigation of accident consequences; the Commission noted that applicants were expected to incorporate into their TSs "those items that are directly related to maintaining the integrity of the physical barriers designed to contain radioactivity," as set forth in the Statement of Consideration, "Technical Specifications for Facility Licenses; Safety Analysis Reports," (33 FR 18610, December 17, 1968). Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.
However, the rule does not specify the particular requirements to be included in a plants TSs.
NRC and industry representatives have developed guidelines for improving the content and quality of nuclear power plant TSs. On February 6, 1987, the Commission issued an interim policy statement on TS improvements, "Interim Policy Statement on Technical Specification Improvements for Nuclear Power Reactors" (52 FR 3788). During the period from 1989 to 1992, the utility owners groups and the NRC staff developed improved STSs, such as NUREG-1430, that would establish model TSs consistent with the Commissions policy for each primary reactor, nuclear steam supply system, and type. In addition, the NRC staff, licensees, and owners groups developed generic administrative and editorial guidelines in the form of a "Writers Guide" for preparing TSs, which gives greater consideration to human factors principles. FirstEnergy followed this guidance in the development of the TS changes proposed in the subject application for DBNPS.
In June 2004, the Commission issued NUREG-1430, Revision 3, which was developed using the guidance and criteria contained in the Commissions Interim Policy Statement. The improved STSs in NUREG-1430 were established as a model for developing improved TSs for Babcock and Wilcox plants in general. The improved STSs reflect the results of a detailed review of the application of the interim policy statement criteria to generic system functions, which were published in a "Split Report" issued to the nuclear steam supply system owners groups in May 1988. The improved STSs also reflect the results of extensive discussions between the owners groups and the NRC staff concerning a number of drafts and revisions, so that application of the Writers Guide and the TS content criteria in 10 CFR 50.36 would consistently reflect detailed system configurations and operating characteristics for all nuclear steam supply system designs. As such, the improved STS Bases presented in NUREG-1430 provide an abundance of generally applicable information regarding the extent to which NUREG-1430 presents requirements that are necessary to protect public health and safety.
With respect to the subject application, Section 3.9, "Refueling Operations," in NUREG-1430 applies to DBNPS.
On July 22, 1993, the Commission issued its Final Policy Statement (58 FR 39132), expressing the view that satisfying the guidance in the policy statement also satisfies Section 182a. of the Act and 10 CFR 50.36. The Final Policy Statement described the safety benefits of the improved STSs, and encouraged licensees to use the improved STSs as the basis for plant-specific license amendments. The scope of such amendments that are based on the STSs range from partial conversions involving changes to one or more individual specifications, to complete conversions of a plants TSs. The subject application for DBNPS proposes a partial conversion of the DBNPS CTSs related to refueling operations. Further, the Final Policy Statement gave guidance for evaluating the required scope of a plants TSs and defined four guidance criteria to be used in determining which existing TS limited condition for operation (LCO) requirements, including any associated Actions and Surveillance Requirements (SRs),
should remain in the TSs. The Commission noted that, in allowing certain items to be relocated to licensee-controlled documents while requiring that other items be retained in the TSs, it was adopting the qualitative standard enunciated by the Atomic Safety and Licensing Appeal Board in Portland General Electric Co. (Trojan Nuclear Plant), ALAB-531, 9 NRC 263, 273 (1979).
There, the Appeal Board observed:
[T]here is neither a statutory nor a regulatory requirement that every operational detail set forth in an applicants safety analysis report (or equivalent) be subject to a technical specification, to be included in the license as an absolute condition of operation which is legally binding upon the licensee unless and until changed with specific Commission approval. Rather, as best we can discern it, the contemplation of both the Act and the regulations is that technical specifications are to be reserved for those matters as to which the imposition of rigid conditions or limitations upon reactor operation is deemed necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety.
By this approach, existing LCO (and associated) requirements that fall within or satisfy any of the criteria in the Final Policy Statement should be retained in the TSs; those LCO (and associated) requirements that do not fall within or satisfy these criteria may be relocated to licensee-controlled documents. The Commission codified the four criteria set out in the Final Policy Statement in 10 CFR 50.36(c)(2)(ii) (60 FR 36953, July 19, 1995). The four criteria are as follows:
Criterion 1 Installed instrumentation that is used to detect, and indicate in the control room (CR), a significant abnormal degradation of the reactor coolant pressure boundary.
Criterion 2 A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 3 A structure, system, or component (SSC) that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 4 A SSC which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
Part 3.0 of this SE provides the basis for the NRC staffs conclusion that the conversion of the DBNPS refueling operations CTSs to PTSs based on corresponding requirements in the STSs and the CTSs, as modified by plant-specific considerations, is consistent with the DBNPS current licensing bases and the requirements and guidance of the Final Policy Statement and 10 CFR 50.36.
3.0 TECHNICAL EVALUATION
The NRC staff has organized this SE by identifying each proposed TS change as belonging to one of the following TS change categories:
Administrative A change that neither reduces nor increases the existing operational limitations and administrative controls for the facility.
More Restrictive A change that increases an existing operational limitation or administrative control, or that adds a new operational limitation or administrative control for the facility.
Less Restrictive A change that reduces or deletes an existing (Specific) operational limitation or administrative control for the facility.
Less Restrictive A change that involves moving detailed technical (Generic) information or requirements, which are inappropriate or unnecessary for inclusion in TSs, to licensee-controlled documents.
Grouping TS changes in these four categories is customary for evaluating applications that propose to convert a facilitys TSs to improved TSs, modeled on the STSs. The following subsections provide detailed discussions of the CTS change categories, and the NRC staffs evaluations of the acceptability of changes under each category.
3.1 Administrative Changes Administrative changes, which are incidental to adopting STS format or phrasing, are intended to incorporate human factors principles into the form and structure of the TSs making them easier to understand and use by plant operations personnel. These changes involve reorganizing, reformatting, and clarifying CTS requirements without affecting technical content or operational restrictions. Among the administrative-type changes proposed by the licensee in the present application, and found acceptable by the NRC staff, are:
Deleting the words "As a minimum" in LCO 3.9.2, consistent with the wording in STSs; Retaining the words "one from each side of the reactor core" in LCO 3.9.2, which is an appropriate plant-specific departure from the wording in STSs; Changing the word "operating" to "OPERABLE" in LCO 3.9.2, consistent with the wording in STSs and the standard definition of OPERABLE in the CTSs and STSs; Clarifying that CHANNEL CALIBRATION in SR 4.9.2 excludes the neutron detectors themselves, consistent with the wording in STSs; Clarifying that in the case where there is no OPERABLE source range neutron flux monitor, ACTION a for only one OPERABLE source range neutron flux monitor must also be performed The NRC staff reviewed all of the administrative changes proposed by the licensee and finds them acceptable because they are consistent with the Writers Guide, STSs, and CTSs; do not result in any substantive change in operating requirements; and are consistent with the Commissions regulations.
3.2 More Restrictive Changes The licensee, in electing to implement the various specifications based on the STSs and the CTSs, proposed requirements that are more restrictive than those in the CTSs. PTSs in this category include requirements that are either new, more conservative than corresponding requirements in the CTSs, or that have additional restrictions that are not in the CTSs but are in the STSs.
Specifically, the DBNPS LCO 3.9.2 ACTION statement would be revised to be similar to the STS ACTION statement, but continue to use the DBNPS TS format and add the STS wording to use the reactor coolant system refueling boron concentration requirement specified in DBNPS LCO 3.9.1. STS ACTION B.2 has no corresponding requirement in the CTSs to verify that boron concentration is within refueling limits. The corresponding STS specification (SR 3.9.1.1) refers to boron concentration limits specified in the COLR [Core Operating Limits Report], whereas the CTS boron concentration is determined from the keff required by LCO 3.9.1 and this difference is reflected in the PTSs. Another proposed change is that the CHANNEL CHECK surveillance be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> throughout MODE 6 operation consistent with the STSs instead of just during CORE ALTERATIONS. Changes such as these that are categorized as more restrictive are acceptable because they place additional limitations on plant operation that enhance safety.
3.3 Less Restrictive Changes (Specific)
Less restrictive requirements include changes, deletions, and relaxations to CTS requirements.
When requirements have been shown to give little or no safety benefit, their removal from the TSs may be appropriate. In most cases, relaxations previously granted to individual plants on a plant-specific basis were the result of (1) generic NRC actions, (2) new staff positions that have evolved from technological advancements and operating experience, or (3) resolution of the owners groups comments during the development of the STSs. The NRC staff reviewed generic relaxations contained in the STSs and found them acceptable because they are consistent with current licensing practices and the Commissions regulations. The licensee did not propose any specific TS changes in this category.
3.4 Less Restrictive Changes (Generic)
When requirements have been shown to give little or no benefit, their removal from the TSs may be appropriate. In most cases, relaxations previously granted to individual plants on a plant-specific basis were the result of (1) generic NRC actions, (2) new staff positions that have evolved from technological advancements and operating experience, or (3) resolution of the owners group comments on STSs.
A proposed change to the CTSs involved revision of the DBNPS SR 4.9.2 to be equivalent to the STS SRs, including deletion of the independent mention of the CHANNEL FUNCTIONAL TEST. Consistent with the STSs, the CHANNEL FUNCTIONAL TEST requirements are not necessary to verify that the source range flux monitors are capable of satisfying the LCO requirements. In MODE 6, the source range flux monitors are required for indication only; there are no required setpoints; and, the source range neutron flux detectors have no control function. The NRC staff reviewed these generic relaxations contained in the PTSs and found them acceptable because they are consistent with current licensing practices and the Commissions regulations.
3.5 DBNPS TS Bases The licensee proposed conforming changes to the Bases for the specifications revised in this amendment. The NRC staff has no objection to these Bases changes.
The licensee stated in its supplemental letter dated April 6, 2005, that the information removed from the TSs and moved to the TS Bases will be adequately controlled under the TS Bases Control Program specified in TS 6.17. This program provides for evaluation of changes in accordance with 10 CFR 50.59 to ensure the Bases are properly controlled. The NRC staff notes that NUREG-1430 Bases B 3.9.2, "Nuclear Instrumentation," clearly states that the source range neutron flux detectors "also provide continuous visual indication in the control room and an audible alarm to alert operators to a possible dilution accident." The licensee further stated that the visual and audible indication features will remain installed in the plant and no changes to the source range indication features are currently contemplated. The NRC staff expects that any future design change reviewed under 10 CFR 50.59 that reduces or eliminates these indication features would warrant prior NRC approval.
4.0 REGULATORY COMMITMENTS The licensees letter dated December 20, 2004, contained the following regulatory commitment:
Associated changes to the TS Bases would be made under the provisions of the TS Bases Control Program. These changes are expected to include additional detail, including a discussion of the visual and audible indication features formerly referenced in the LCO.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (70 FR 7765). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 CONCLUSION
The NRC staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: W. Macon Date: September 12, 2005