ML070300020
| ML070300020 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/13/2007 |
| From: | Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Thomas J. Palmisano Nuclear Management Co |
| M. Chawla LPL3-1 | |
| Shared Package | |
| ML070300017 | List: |
| References | |
| TAC MD0061, TAC MD0062 | |
| Download: ML070300020 (11) | |
Text
February 13, 2007 Mr. Thomas J. Palmisano 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: LICENSE AMENDMENT REQUEST FOR MISCELLANEOUS TECHNICAL SPECIFICATION ADMINISTRATIVE CHANGES (TAC NOS. MD0061 AND MD0062)
Dear Mr. Palmisano:
The Commission has issued the enclosed Amendment No. 176 to Facility Operating License No. DPR-42 and Amendment No. 166 to Facility Operating License No. DPR-60 for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated February 13, 2006.
The amendments revise PINGPs Technical Specifications (TS) to change the wording in TS 3.0, Surveillance Requirement (SR) Applicability and change format and titles in TS 5.0, Administrative Controls. The proposed changes improve conformance with the industry standard, NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 3.0, and also improve the technical accuracy and usability of the TS.
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. 176 to DPR-42
- 2. Amendment No. 166 to DPR-60
- 3. Safety Evaluation cc w/encls: See next page
PKG ML07030017 Amendment: ML070300020 Tech Specs: ML070460318 OFFICE NRR/LPL3-1 NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/ITSB OGC NRR/LPL3-1/BC(A)
NAME JPoole MChawla THarris Kobetz SHamrick PMilano DATE 2/6/07 2/6/07 1/6/07 2/8/07 2/9/07 2/13/07
Prairie Island Nuclear Generating Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 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 Generals 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 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 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 Michael B. Sellman President and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016 July 2006
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 176 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 February 13, 2006, 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. 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/
Patrick D. Milano, Acting 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: February 13, 2007
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 166 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 February 13, 2006, 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. 166, 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/
Patrick D. Milano, Acting 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: February 13, 2007
ATTACHMENT TO LICENSE AMENDMENT NOS. 176 AND 166 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 3.0-5 3.0-5 3.0-6 3.0-6 5.0-10 5.0-10 5.0-34 5.0-34 5.0-35 5.0-35 5.0-36 5.0-36
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 176 TO FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO. 166 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 February 13, 2006, 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 TS to change the wording in TS 3.0, Surveillance Requirement (SR) Applicability and change format and titles in TS 5.0, Administrative Controls. The proposed changes improve conformance with the industry standard, NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 3.0, and also improve the technical accuracy and usability of the TS.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TSs are derived from the plant safety analyses.
The staff reviewed the proposed changes for compliance with Title 10 of the Code of Federal Regulations (10 CFR) 10 CFR 50.36, and agreement with the precedent as established in NUREG-1431. In general, licensees cannot justify TS changes solely on the basis of adopting the model standard TS. To ensure this, the staff makes a determination that proposed changes maintain adequate safety. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification.
In general, there are two classes of changes to TSs: (1) changes needed to reflect contents of the design-basis (TSs are derived from the design-basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TSs over time. This amendment deals with the second class of change; namely, administrative changes that reflect the current configuration of the plant.
Licensees may revise the TSs to adopt improved standard TS format and content provided that plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides clarification (i.e., no requirements are materially altered),
(2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance, are discussed in Section 3.0 in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The Licensees TS revision proposes to make changes that are editorial, administrative or provide clarification. In order for these changes to be acceptable the staff must determine that the editorial, administrative and clarification changes do not alter the TS requirements.
The licensee proposes to revise the following PINGP TS:
3.1 TS 3.0, Surveillance Requirement (SR) Applicability The current page header for TS 3.0, Surveillance Requirement (SR) Applicability is LCO
[Limiting Condition for Operation] Applicability. This header is not consistent with the contents of this TS section and is not consistent with the format guidance of NUREG-1431. The License Amendment Request (LAR) proposes to replace the current page header with SR Applicability.
In the last paragraph of Section 3.0.4, MODES, which is a TS defined term, is incorrectly spelled with a lower case s. This is not consistent with the format guidance of NUREG-1431 which capitalizes defined terms. These changes are acceptable since they are administrative and conform with the guidance of NUREG-1431.
3.2 TS 5.0, Administrative Controls Sections 5.5 and 5.6 The LAR proposes to delete the underline under (continued) on page 5.0-10. Furthermore, in TS 5.6.5, P is deleted from the number for reference 1 which becomes NSPNAD-8101-A;
-P-A is added to number for reference 9 which becomes WCAP-13677-P-A, and an extra space is removed prior to the document number for references 24 and 26. These changes are acceptable because they are administrative and improve the accuracy of the TS.
4.0
SUMMARY
The licensees proposed changes in this LAR are editorial in nature, reflect the current configuration of the plant and do not change the TS requirements. The NRC staff finds the proposed changes are technically justified, comply with 10 CFR 50.36 and are consistent with the standard TSs. On this basis, the Nuclear Regulatory Commission staff concludes that the proposed changes to the TS of the PINGP are acceptable.
5.0 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.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the 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 (71 FR 18375). 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 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 C. Hearn Date: February 13, 2007