ML081430127
| ML081430127 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  (DPR-042, DPR-060) |
| Issue date: | 07/18/2008 |
| From: | Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Wadley M Nuclear Management Co |
| Chawla M, NRR/DORL/LPL3-1, 301-415-8371 | |
| Shared Package | |
| ML081430161 | List: |
| References | |
| TAC MD6120, TAC MD6121 | |
| Download: ML081430127 (15) | |
Text
July 18, 2008 Mr. Michael D. Wadley Site Vice President Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089
SUBJECT:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: ADOPTING PROVISIONS OF REGULATORY GUIDE (RG) 1.52 REVISION 3 (TAC NOS. MD6120 AND MD6121)
Dear Mr. Wadley:
The Commission has issued the enclosed Amendment No.186 to Facility Operating License No.
DPR-42 and Amendment No.176 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated July 19, 2007, Agencywide Documents Access and Management System (ADAMS) Accession No. ML072010452, as supplemented by letter dated June 25, 2008, ADAMS Accession No. ML081780566.
The amendments revise the Prairie Island Nuclear Generating Plant TS for Units 1 and 2. The requested revision includes TS 3.6.9, Shield Building Ventilation System (SBVS), TS 3.7.12, Auxiliary Building Special Ventilation System (ABSVS), TS 3.7.13, Spent Fuel Pool Special Ventilation System (SFPSVS), and TS 5.5.9, Ventilation Filter Testing Program (VFTP).
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
- 1. Amendment No.186 to DPR-42
- 2. Amendment No.176 to DPR-60
- 3. Safety Evaluation cc w/encls: See next page
The amendments revise the Prairie Island Nuclear Generating Plant TS for Units 1 and 2. The requested revision includes TS 3.6.9, Shield Building Ventilation System (SBVS), TS 3.7.12, Auxiliary Building Special Ventilation System (ABSVS), TS 3.7.13, Spent Fuel Pool Special Ventilation System (SFPSVS), and TS 5.5.9, Ventilation Filter Testing Program (VFTP).
A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Mahesh L. Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosures:
- 1. Amendment No.186 to DPR-42
- 2. Amendment No.176 to DPR-60
- 3. Safety Evaluation DISTRIBUTION PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 RidsNrrPMMChawla RidsNrrDirsltsb RidsNrrLATHarris RidsOGCRp RidsAcrsAcnw&mMailCenter G. Hill, OIS RidsRgn3MailCenter RidsNrrDorlDpr Package Number: ML081430161 Amendment Number: ML081430127 TS Accession Number: ML082050445 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/SCVB/BC NRR/ITSB/BC OGC/NLO NRR/LPL3-/BC NAME MChawla THarris RDennig RElliot MSpencer LJames DATE 07/ 16 /08 07 / 01 /08 07/18/08 07 / 17 /08 07 / 16 /08 07 / 18 /08
NUCLEAR MANAGEMENT COMPANY, LLC DOCKETNO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.186 License No. DPR-42
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nuclear Management Company, LLC (the licensee), dated July 19, 2007, 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. DPR-42 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.186, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Lois M. James, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: July 18, 2008
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 License No. DPR-60
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nuclear Management Company, LLC (the licensee), dated July 19, 2007, 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. DPR-60 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.176, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 90 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Lois M. James, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: July 18, 2008
ATTACHMENT TO LICENSE AMENDMENT NOS.186 AND 176 FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 Replace the following pages of the Facility Operating License No. DPR-42 and DPR-60 with the attached revised pages. The changed areas are identified by a marginal line.
REMOVE INSERT DPR-42, License Page 3 DPR-42, License Page 3 DPR-60, License Page 3 DPR-60, License 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 3.6.9-1 3.6.9-1 3.7.12-2 3.7.12-2 3.7.13-2 3.7.13-2 5.0-23 5.0-23 (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, NMC to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6)
Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purpose of volume reduction and decontamination.
C.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.186, are hereby incorporated in the license. NMC shall operate the facility in accordance with the Technical Specifications.
(3) Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 1, submitted by letters dated October 18, 2006, and January 10, 2007.
Unit 1 Amendment No. 186
(5)
Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, NMC to transfer byproduct materials from other job sites owned by Northern States Power Company for the purposes of volume reduction and decontamination.
C.
This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter l: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level NMC is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.176, are hereby incorporated in the license. NMC shall operate the facility in accordance with the Technical Specifications.
(3)
Physical Protection NMC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled:
'Prairie Island Nuclear Generating Plant Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program," Revision 1, submitted by letters dated October 18, 2006, and January 10, 2007.
Unit 2 Amendment No.176
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.186 TO FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO.176 TO FACILITY OPERATION LICENSE NO. DPR-60 NUCLEAR MANAGEMENT COMPANY, LLC PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306
1.0 INTRODUCTION
By application dated July 19, 2007, Agencywide Documents Access and Management System (ADAMS) Accession No. ML072010452, as supplemented by letter dated June 25, 2008, ADAMS Accession No. ML081780566, the Nuclear Management Company, LLC (the licensee),
requested changes to the Technical Specifications (TSs) for the Prairie Island Nuclear Generating Plant, (PINGP) Units 1 and 2. The proposed changes would revise the PINGP TSs for Units 1 and 2. The requested revision includes:
TS 3.6.9, Shield Building Ventilation System (SBVS),
TS 3.7.12, Auxiliary Building Special Ventilation System (ABSVS),
TS 3.7.13, Spent Fuel Pool Special Ventilation System (SFPSVS),
TS 5.5.9, Ventilation Filter Testing Program (VFTP).
The specific changes in this license amendment will revise the duration of the heater tests and the frequency for performance of filter tests for these systems and the Control Room Special Ventilation System in accordance with the guidance of Regulatory Guide (RG) 1.52 Revision 3, Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants, (RG 1.52 Rev. 3).
The information contained in the June 25, 2008, supplement is clarifying in nature and does not change either the scope of the amendment request or the no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
The construction of the PINGP was significantly complete prior to issuance of 10 CFR Part 50, Appendix A, General Design Criteria (GDC). PINGP was designed and constructed to comply with the Atomic Energy Commission (AEC) GDC as proposed on July 10, 1967, as described in the plant updated safety analysis report.
By letter dated January 8, 1975, the AEC requested the PINGP licensee to submit proposed TS for SBVS, ABSVS and SFPSVS consistent with the guidance of RG 1.52, dated June 1973. The Nuclear Regulatory Commission (NRC) issued license Amendments 17 and 11 for Units 1 and 2 respectively, on October 14, 1976, which introduced requirements in the PINGP TS to operate each safeguards filtration train for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month with the heaters on. The requirements have remained substantively unchanged since that time.
In accordance with 10 CFR 50.36, Technical Specifications surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
One acceptable method to meet the requirements of 10 CFR 50.36 for the in-place testing of engineered-safety-feature (ESF) atmosphere cleanup systems and laboratory testing of activated carbon, is contained in regulatory position C.6 and C.7 respectively of RG 1.52 Rev 3.
Regulatory position C.6 states, in part, that the initial in-place acceptance testing of ESF atmosphere cleanup systems and components should be performed in accordance with Section TA of the American Society of Mechanical Engineers, Code on Nuclear Air and Gas Treatment, 1997 (ASME AG-1-1997).
Periodic, in-place testing of ESF atmosphere cleanup systems and components should be performed in accordance with American Society of Mechanical Engineers, Testing of Nuclear Air-Treatment Systems, 1989 (ASME N510-1989) as modified and supplemented. Regulatory position C.7 states, in part, that laboratory testing of samples of activated carbon adsorber material from ESF atmosphere cleanup systems should be performed in accordance with ASTM D3803-1989 and Table 1 of RG 1.52 Rev 3 as supplemented.
In regulatory position C.6.1, the staff specified that each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes each month, with the heaters on (if so equipped), to justify the operability of the system and all its components. In regulatory position C.6.3, C.6.4, the staff in part recommended that in-place leak testing for adsorbers and in-place aerosol leak testing for HEPA filters upstream from carbon adsorbers in ESF atmosphere cleanup systems should be performed at least once each 24 months. Regulatory position C.7.2 states, in part, that sampling and analysis should be performed after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation, or at least once each 24 months, whichever comes first.
3.0 TECHNICAL EVALUATION
Currently TS surveillance requirements (SR) 3.6.9.1, 3.7.12.1, and 3.7.13.1, require their filtration train to be operated for 10 or more hours every 31 days with the heaters on. TS 5.5.9 requires performance of the test in the VFTP each operating cycle or 18 months for shared systems. The proposed revisions will incorporate system and filter testing changes consistent with RG 1.52 Rev 3.
TS 3.6.9, Shield Building Ventilation System (SBVS)
With regard to TS 3.6.9, the SBVS is required by AEC GDC 70, Control of Releases of Radioactivity to the Environment, to ensure that radioactive materials that leak from the primary containment into the shield building following a design-basis accident are filtered and adsorbed prior to exhausting to the environment.
The SBVS consists of two separate and redundant trains. Each train includes a heater, a prefilter, moisture separators, a high efficiency particulate air (HEPA) filter, an activated charcoal adsorber section for removal of radioiodines, a recirculation fan and an exhaust fan. The prefilters remove large particles in the air, and the moisture separators remove entrained water
droplets present, to prevent excessive loading of the HEPA filters and charcoal adsorbers.
Heaters are included to reduce the relative humidity of the airstream. The moisture separators function to reduce the moisture content of the airstream. The ventilation system for each shield building includes a vent stack which penetrates the shield building dome and discharges to the atmosphere.
This license amendment request (LAR) proposes to revise SR 3.6.9.1 to require testing for greater than or equal to 15 minutes every 31 days. The licensee stated and the staff agrees that testing the heaters for 15 minutes is sufficient to verify that the safety function of the heaters is met, and that this change does not reduce the safety of the system. The staff finds that this change is acceptable because it maintains safety and follows the guidance of RG 1.52 Rev 3.
TS 3.7.12, Auxiliary Building Special Ventilation System (ABSVS)
The ABSVS is a standby ventilation system, common to the two PINGP units, that is designed to collect and filter air from those areas within the auxiliary building which have the potential for collecting significant containment leakage that could bypass the shield building and leakage from systems which could recirculate primary coolant during loss-of-coolant accident mitigation.
The ABSVS consists of two independent and redundant trains. Each train consists of a heater, a prefilter, a HEPA filter, an activated charcoal adsorber section for removal of gaseous activity, and a fan. The prefilters remove any large particles in the air, and with the heaters, reduce the level of entrained water droplets present to prevent excessive loading of the HEPA filters and charcoal adsorbers. The primary purpose of the heaters is to maintain the relative humidity at an acceptable level.
The licensee stated that this LAR proposes to revise SR 3.7.12.1 to require testing for greater than or equal to 15 minutes every 31 days. The staff believes that testing the heaters for 15 minutes is sufficient to verify that the safety function of the heaters is met and, that this change does not reduce the safety of the system. Therefore, the staff finds this change acceptable because it does not reduce the safety of the system and it incorporates the guidance of RG 1.52, Revision 3.
TS 3.7.13, Spent Fuel Pool Special Ventilation System (SFPSVS)
The SFPSVS refers to that portion of the Spent Fuel Special and Containment Inservice Purge system that filters airborne radioactive particulates from the spent fuel pool enclosure following a fuel-handling accident in that area. The Spent Fuel Pool Special Ventilation fans exhaust air to prefilter-absolute-charcoal filters, then to the associated Shield Building vent stack. The SFPSVS consists of two independent and redundant trains, each capable of meeting the design requirements. Each train consists of a heater, a prefilter, a HEPA filter, an activated charcoal adsorber section for removal of gaseous activity, and a fan. Heaters function to reduce the relative humidity of the airstream.
This LAR proposes to revise SR 3.7.13.1 to require testing for greater than or equal to 15 minutes every 31 days. As stated above regarding the ABSVS, the staff believes that testing the heaters for 15 minutes is sufficient to verify that the safety function of the heaters is met and, that this change does not reduce the safety of the system. Because this change does not reduce safety, the staff agrees with the licensees statement that it is acceptable because it incorporates the guidance of RG 1.52, Revision 3.
TS 5.5.9, Ventilation Filter Testing Program (VFTP)
Currently, TS 5.5.9 requires testing under the ventilation filter testing program to be performed each operating cycle (18 months for shared systems). The proposed change is to require testing in accordance with the ventilation filter testing program to be performed at least once each 24 months.
The licensee stated that the 24 months frequency proposed in this LAR will be the maximum time between scheduled tests. The licensee also stated that the testing may be performed on more frequent basis under its VFTP. This includes filter testing after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation or following painting, fire or chemical release in any ventilation zone communicating with the system that could contaminate the HEPA filters or charcoal adsorbers.
TS 5.5.9 concludes with the statement, The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test Frequencies. The PINGP TS SR 3.0.2 includes the unique limitation, The specified Frequency is met for each SR with a specified Frequency of 24 months if the Surveillance is performed within 24 months. Thus, the reference to SR 3.0.2 in TS 5.5.9 does not allow scheduling these tests specified as 24 months for any interval beyond 24 months.
The NRC staff understands that the intent of the requested change is to change the frequency of testing from 18 months as currently described in TS 5.5.9.a, b and c VFTP to 24 months as described in Regulatory Position C.6.3, C.6.4 and C.7.2 of RG 1.52, Rev 3. TS 5.5.9 a, b, and c involve in-place leak testing of the HEPA filter, in-place leak testing of the charcoal adsorber, and laboratory testing of a charcoal adsorber sample in accordance with ASTM-D3803-1989, respectively.
Also, the 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation specified as a maximum interval for laboratory testing of charcoal adsorber samples above, was specified in RG 1.52 Rev.2, and did not change in RG 1.52, Rev.3. Because the licensees USAR relies upon filter testing conditions per the VFTP to envelope expected worst-case operating conditions, the NRC staff expects that any changes to the 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> limitation in the VFTP will be subject to the change process in 10 CFR 50.59. The staffs review and assessment is based upon guidance of RG 1.52, Rev.3; consequently the staff finds the requested change acceptable.
With respect to TS 5.5.9.d and e VFTP, which concern the pressure drop across the combined HEPA filters and charcoal adsorbers, and concern filter test face velocities in laboratory tests of charcoal adsorber samples, the staff notes that these tests, regardless of the results, are not accident initiators and as such do not involve an increase in the probability of an accident. It is the staffs judgment that the change in testing frequency from 18 months to 24 months is reasonable because the environment and normal operating conditions for the systems associated with TS 5.5.9.d and e are not severe and a test frequency of every 24 months provides an adequate check on these systems. The staff determined that the proposed change is consistent with the intent of current regulatory guidance for these systems and will continue to provide assurance that these systems will perform their intended functions. Therefore, the staff finds the proposed change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Minnesota State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes surveillance requirements. The 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 (72 FR 57355). 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.
6.0 CONCLUSION
This LAR proposes TS changes which reduce the duration of safeguards ventilation system heater testing requirements and extend the frequency for filter testing. These changes are consistent with the guidance of RG 1.52, Rev 3. Therefore, 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: Harold Walker Date: July 18, 2008
July 2006 Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Peter M. Glass Assistant General Counsel Xcel Energy Services, Inc.
414 Nicollet Mall Minneapolis, MN 55401 Manager, Regulatory Affairs Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089 Manager - Environmental Protection Division Minnesota Attorney General=s Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127 U.S. Nuclear Regulatory Commission Resident Inspector's Office 1719 Wakonade Drive East Welch, MN 55089-9642 Administrator Goodhue County Courthouse Box 408 Red Wing, MN 55066-0408 Commissioner Minnesota Department of Commerce 85 7th Place East, Suite 500 St. Paul, MN 55101-2198 Tribal Council Prairie Island Indian Community ATTN: Environmental Department 5636 Sturgeon Lake Road Welch, MN 55089 Nuclear Asset Manager Xcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401 Dennis L. Koehl Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Joel P. Sorenson Director, Site Operations Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Drive East Welch, MN 55089