ML081780165
| ML081780165 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/05/2008 |
| From: | Peter Bamford NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Pardee C Exelon Generation Co |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| Shared Package | |
| ml081780155 | List: |
| References | |
| TAC MD7508, TAC MD7509 | |
| Download: ML081780165 (15) | |
Text
August 5, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generating Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS (TAC NOS. MD7508 AND MD7509)
Dear Mr. Pardee:
The Commission has issued the enclosed Amendment No. 192 to Facility Operating License No. NPF-39 and Amendment No. 153 to Facility Operating License No. NPF-85, for Limerick Generating Station, Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 12, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML073461114), as supplemented by letter dated June 11, 2008 (ADAMS Accession No. ML081630383).
The amendments consist of changes to the TSs of each unit regarding administrative issues involving: (1) index corrections; (2) removing requirements or notes that are no longer applicable; (3) deleting references to previously deleted requirements; (4) changing references to the location of previously relocated information; and (5) editorial corrections.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/ra/
Peter Bamford, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosures:
- 1. Amendment No. 192 to License No. NPF-39
- 2. Amendment No. 153 to License No. NPF-85
- 3. Safety Evaluation cc w/encls: See next page
August 5, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generating Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS (TAC NOS. MD7508 AND MD7509)
Dear Mr. Pardee:
The Commission has issued the enclosed Amendment No. 192 to Facility Operating License No. NPF-39 and Amendment No. 153 to Facility Operating License No. NPF-85, for Limerick Generating Station, Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 12, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML073461114), as supplemented by letter dated June 11, 2008 (ADAMS Accession No. ML081630383).
The amendments consist of changes to the TSs of each unit regarding administrative issues involving: (1) index corrections; (2) removing requirements or notes that are no longer applicable; (3) deleting references to previously deleted requirements; (4) changing references to the location of previously relocated information; and (5) editorial corrections.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/ra/
Peter Bamford, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosures:
- 1. Amendment No. 192 to License No. NPF-39
- 2. Amendment No. 153 to License No. NPF-85
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1-2 Resource RidsNrrPMPBamford Resource RidsNrrLAABaxter Resource GHill,OIS (2)
RidsNrrDorlDpr Resource RidsRgn1MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDirsItsb Resource RidsOgcRp Resource MHamm, NRR LPL1-2 R/F Package Accession Number: ML081780155; Amendment Accession Number: ML081780165; Tech Specs for Amd 192: ML08170254; Tec Specs for Amd 153: ML081780287 LPLI-2/PM LPLI-2/LA ITSB/BC OGC LPLI-2/BC Name PBamford ABaxter RElliott BMizuno HChernoff Date 6/26/08 7/1/08 7/24/08 7/25/08 8/5/08 Official Record Copy
Limerick Generating Station, Unit Nos. 1 and 2 cc:
Christopher Mudrick Site Vice President Limerick Generating Station Exelon Generation Company, LLC 3146 Sanatoga Road Sanatoga, PA 19464 Ed Callan, Plant Manager Limerick Generating Station Exelon Generation Company, LLC 3146 Santoga Road Sanatoga, PA 19464 Manager Regulatory Assurance - Limerick Generating Station Exelon Generation Company, LLC 3146 Sanatoga Road Sanatoga, PA 19464 Senior Vice President - Mid-Atlantic Operations Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Chief Operating Officer-Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President -Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director, Licensing and Regulatory Affairs Exelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Manager Licensing Exelon Generation Company, LLC Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Correspondence Control Desk Exelon Generation Company, LLC 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector U.S. Nuclear Regulatory Commission Limerick Generating Station P.O. Box 596 Pottstown, PA 19464 Library U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Director, Bureau of Radiation Protection Pennsylvania Dept. of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Chairman Board of Supervisors of Limerick Township 646 West Ridge Pike Linfield, PA 19468 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803
Limerick Generating Station, Unit Nos. 1 and 2 cc:
J. Bradley Fewell, Esquire Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 192 License No. NPF-39
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee), dated December 12, 2007, supplemented by letter dated June 11, 2008, 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-39 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 192, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: August 5, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 192 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following page of the Facility Operating License with the revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 3 Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert ii ii xxvii xxvii 3/4 1-11 3/4 1-11 3/4 1-12 3/4 1-12 3/4 3-68 3/4 3-68 3/4 3-110 3/4 3-110 3/4 4-8 3/4 4-8 3/4 5-1 3/4 5-1 3/4 6-17 3/4 6-17 3/4 6-49 3/4 6-49 3/4 6-51 3/4 6-51 3/4 6-51a 3/4 6-51a 3/4 7-4 3/4 7-4 3/4 8-9 3/4 8-9 3/4 8-21 3/4 8-21
EXELON GENERATION COMPANY, LLC DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. NPF-85
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee), dated December 12, 2007, supplemented by letter dated June 11, 2008, 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-85 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 153, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ra/
Harold K. Chernoff, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: August 5, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 153 FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following page of the Facility Operating License with the revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert Page 3 Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert ii ii xxvii xxvii 1-4 1-4 3/4 3-68 3/4 3-68 3/4 3-110 3/4 3-110 3/4 4-8 3/4 4-8 3/4 4-8a 3/4 4-8a 3/4 5-1 3/4 5-1 3/4 6-10 3/4 6-10 3/4 6-17 3/4 6-17 3/4 6-49 3/4 6-49 3/4 6-51 3/4 6-51 3/4 6-51a 3/4 6-51a 3/4 7-6a 3/4 7-6a 3/4 8-9 3/4 8-9 3/4 8-21 3/4 8-21
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 192 TO FACILITY OPERATING LICENSE NO. NPF-39 AND AMENDMENT NO. 153 TO FACILITY OPERATING LICENSE NO. NPF-85 EXELON GENERATION COMPANY, LLC LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353
1.0 INTRODUCTION
By application dated December 12, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML073461114), as supplemented by letter dated June 11, 2008 (ADAMS Accession No. ML081630383), Exelon Generation Company, LLC (Exelon, the licensee) requested changes to the Technical Specifications (TSs) for Limerick Generating Station (LGS), Units 1 and 2. The proposed changes would revise the TSs of each unit to reflect various administrative changes involving: (1) index corrections; (2) removing requirements or notes that are no longer applicable; (3) deleting references to previously deleted requirements; (4) changing references to the location of previously relocated information; and (5) editorial corrections. The supplement provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC or Commission) staff=s original proposed no significant hazards consideration determination as published in the Federal Register on May 6, 2008 (73 FR 25040).
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act of 1954, as amended, requires all applicants for nuclear power plant licenses to include technical specifications as part of the license. Included in the criteria that the TS must cover are: (1) the specific characteristics of the facility; and (2) other such information deemed by the Commission necessary to ensure 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.
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36 specifies the categories and criteria for information that must be included in the TSs. These include the following: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
Since the LGS, Units 1 and 2, operating licenses and construction permits were issued after January 16, 1969, the TS requirements described above are applicable to each unit pursuant to 10 CFR 50.36(e).
3.0 TECHNICAL EVALUATION
The changes associated with this license amendment request (LAR) are described below. They are grouped by category in order to facilitate the evaluation.
3.1 Index Corrections The LAR proposes to revise Index page ii for LGS, Units 1 and 2 to reflect the previously approved addition of TS Definition 1.35, RECENTLY IRRADIATED FUEL to TS page 1-6 and TS Definition 1.37a, RESTRICTED AREA to TS page 1-7, along with the appropriate renumbering of the remaining TS definitions. The previous approval for the definition of RECENTLY IRRADIATED FUEL was granted via license amendment numbers 185 (Unit 1) and 146 (Unit 2), by letter dated August 23, 2006 (ADAMS Accession No. ML062210214). The previous approval for the definition of RESTRICTED AREA was granted via license amendment numbers 187 (Unit 1) and 148 (Unit 2), by letter dated June 29, 2007 (ADAMS Accession No. ML071760167). The changes to the index pages described in this LAR should have been made along with license amendments listed above. This change provides consistency between the index and the TS pages, corrects an oversight from the previous amendments, is administrative in nature with no impact on plant safety, and is, therefore, acceptable.
The LAR proposes to change the word Semiannual to Annual in the title of the Radioactive Effluent Release Report on TS Index page xxvii to reflect the appropriate title for the report as specified under Section 6.9.1, Routine Reports, on TS page 6-17. The change from a semiannual to an annual Radioactive Effluent Release Report was authorized by license amendment numbers 73 (Unit 1) and 35 (Unit 2) via letter dated August 10, 1994 (ADAMS Accession No. ML011560018). The changes to the index pages described in this LAR should have been made along with license amendments 73 (Unit 1) and 35 (Unit 2). This change provides consistency between the index and the TS pages, corrects an oversight from the previous amendments, is administrative in nature with no impact on plant safety, and is, therefore, acceptable.
3.2 Cycle-Specific Requirements or Notes that are No Longer Applicable The LAR requests the deletion of Limiting Condition for Operation (LCO) 3.1.3.6, Action c. and associated Surveillance Requirement (SR) 4.1.3.6.d, relative to repositioning uncoupled control rod 50-27 for LGS, Unit 1. It would also delete the words except as in 3.1.3.6.c or from LCO 3.1.3.6, Action a.2. These specifications were inserted into the LGS, Unit 1 TSs via license amendment number 124, as described in letter dated January 16, 1998 (ADAMS Accession No. ML011570154). The specifications associated with this uncoupled rod were specifically limited to operation of LGS, Unit 1, for the duration of cycle 7. Rod coupling was restored prior to operation in cycle 8 and LGS, Unit 1 is currently operating in cycle 12. Therefore, the specifications associated with the formerly uncoupled rod 50-27 are no longer applicable, do not serve a useful function in the LGS, Unit 1 TSs, and their removal will have no impact on plant safety. On this basis, the NRC staff finds these changes to be acceptable.
The LAR proposes to delete the double asterisk and associated footnote from the 145 degree Fahrenheit drywell average air temperature limit specified in TS LCO 3.6.1.7 for LGS, Unit 2 and the associated TS Action. This footnote was added due to the inoperability of two of the LGS, Unit 2 drywell unit cooler fans in accordance with license amendment number 145 as described by letter dated July 7, 2006 (ADAMS Accession No. ML061880495). The change was limited to LGS, Unit 2, cycle 9 only. The fans were repaired in the refueling outage following LGS, Unit 2 cycle 9 and the unit is currently operating in cycle 10. Therefore, the specifications associated with the allowed deviation from the 145 degree drywell air temperature limit in the LGS, Unit 2 TSs are no longer applicable, and their removal will have no impact on plant safety. On this basis, the NRC staff finds these changes to be acceptable.
3.3 References to Previously Deleted Requirements The LAR requests that the reference to TS SR 4.8.1.1.3 be deleted from TS SR 4.8.1.2 on TS page 3/4 8-9 in the LGS, Units 1 and 2 TSs. TS SR 4.8.1.1.3 formerly involved the submission of a special report on emergency diesel generator (EDG) failures. This reporting requirement was previously deleted by amendment numbers 189 (Unit 1) and 150 (Unit 2) via letter dated November 6, 2007 (ADAMS Accession No. ML072760080). The deletion of TS SR 4.8.1.1.3 was evaluated and found acceptable by the NRC staff in these previous amendments.
Therefore, the change described in the LAR provides consistency between the TS sections, corrects an oversight from the previous amendments, is administrative in nature, has no impact on plant safety, and is, therefore, acceptable.
3.4 References to the Location of Previously Relocated Information The LAR requests that the word UFSAR [Updated Final Safety Analysis Report] be replaced with the word TRM [Technical Requirements Manual] in the relocation information provided on TS pages 3/4 3-68, 3/4 3-110, 3/4 6-49, 3/4 6-51, 3/4 6-51a, and 3/4 8-21 for LGS, Units 1 and 2. Previous amendments have been approved which relocated the requirements formerly on these pages to the UFSAR. These past amendments are summarized below:
Item Title Approval Letter Date Amendment Number (Unit 1/Unit 2)
ADAMS Accession Number Seismic Monitoring August 29, 1994 75/36 ML011550325 Turbine Overspeed August 24, 1995 100/64 ML011570235 Reactor Enclosure and Refueling Area Secondary Containment Isolation Valves November 20, 1995 105/69 ML011560056 Primary Containment Penetration Devices June 22, 1995 93/57 ML011560083 The reason a change from UFSAR to TRM is requested is to clarify the current location of these formerly TS items. Subsequent to the approval of the relocations to the UFSAR listed above, LGS has implemented a TRM program which, under licensee control, consolidates licensing commitments related to equipment that does not require TS controls for operational convenience. When the NRC staff approved the relocation of each of the parameters listed above out of the TSs, a key factor in allowing the changes was the control of the relocated information in the UFSAR under 10 CFR 50.59. Thus, in order to maintain consistency with the original NRC staff rationale for approving the changes, if a licensee chooses to relocate this information from the UFSAR to the TRM, the information in TRM must be controlled as if it were UFSAR information. As a result of the issuance of LGS amendment numbers 191 (Unit 1) and 152 (Unit 2), via letter dated May 29, 2008 (ADAMS Accession No. ML080870376), LGS is required to explicitly state in their UFSAR that information in the TRM is to be treated at the same level as information presented in the UFSAR. Therefore, the original basis for the NRC staff approval of the relocation of these components out of the TS is maintained, and the change of the relocation information wording in the TS from the UFSAR to the TRM will have no impact on plant safety or the regulatory process and is, therefore, acceptable.
3.5 Editorial Changes The following editorial changes are proposed in the LAR. All are typographical or grammatical in nature and thus only impact administrative requirements.
For LGS, Unit 2 - Capitalize the first letter r in the word radioactive in the title of the Radioactive Effluent Controls Program referenced under Item No. (1) in TS Definition 1.24 (OFFSITE DOSE CALCULATION MANUAL) on TS page 1-4. This is grammatically appropriate for the title of a program and has no impact on plant safety. Therefore the change is acceptable.
For LGS, Unit 2 - Replace misspelled word RELOCATD with the word RELOCATED on TS page 3/4 3-110. This is grammatically appropriate and has no impact on plant safety. Therefore the change is acceptable.
For LGS, Units 1 and 2 - Replace capitalized word INOPERABLE with lower case word inoperable in TS LCO 3.4.3.1, Actions B, C, D, and E on TS page 3/4 4-8. Since inoperable is not a defined term in section 1.0 of the TS this will maintain convention. This change will not change the meaning of the word inoperable, will have no impact on plant safety, and is, therefore, acceptable.
For LGS, Unit 2 - Replace the word or with the word of in TS SR 4.4.3.1.b on TS page 3/4 4-8a. The use of the word or in this sentence makes it nonsensical. The word of is grammatically appropriate and consistent with the companion surveillances (SR 4.4.3.1a, c and d). Hence, this change corrects an obvious typographical error, makes the surveillance read properly, has no impact on plant safety, and is, therefore, acceptable.
For LGS, Units 1 and 2 - Replace the word patch with the word path in TS LCO 3.5.1.a.2 on TS page 3/4 5-1. The use of the phrase flow patch in this sentence makes it nonsensical. The phrase flow path is grammatically appropriate and consistent with the companion surveillances (SR 3.5.1.b.2 and SR 3.5.1.c.2). Hence, this change corrects obvious typographical errors, makes the surveillances read properly, has no impact on plant safety and is, therefore, acceptable.
For LGS, Units 1 and 2 - Delete the s at the end of the word valves and replace the word the with the word each in TS LCO 3.6.3 on TS page 3/4 6-17. This makes the number agreement in the sentence grammatically correct, has no impact on plant safety, and is, therefore, acceptable.
For LGS, Unit 1 - Change the paragraph indent for TS SR 4.7.1.2.b.2 to line up with the paragraph indent for TS SR 4.7.1.2.b.1 on TS page 3/4 7-4. This change only impacts the page layout, has no impact on plant safety and is, therefore, acceptable.
For LGS, Unit 2 - Delete the duplicate word both from the first sentence in TS LCO 3.7.2, Action b.2 on TS page 3/4 7-6. This corrects an obvious typographical error, makes the sentence grammatically correct, has no impact on plant safety and is, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The portions of this amendment described in Sections 3.2 and 3.4 of this evaluation change 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 effluents 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 (73 FR 25040). 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.
The portions of this amendment described in Sections 3.1, 3.3 and 3.5 of this evaluation change administrative or recordkeeping requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents 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 (73 FR 25040). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10)(ii). 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.
6.0 CONCLUSION
The Commission 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Peter Bamford Date: August 5, 2008