ML080390090
| ML080390090 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/25/2008 |
| From: | Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | Wadley M Nuclear Management Co |
| Chawla M, NRR/.DLPM, 415-8371 | |
| Shared Package | |
| ml080390099 | List: |
| References | |
| TAC MD4850, TAC MD4851 | |
| Download: ML080390090 (15) | |
Text
February 25, 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: REVISE TECHNICAL SPECIFICATION 5.2.2 AND TECHNICAL SPECIFICATION 5.3 QUALIFICATION REQUIREMENTS FOR SHIFT TECHNICAL ADVISORS (TAC NOS. MD4850 AND MD4851)
Dear Mr. Wadley:
The Commission has issued the enclosed Amendment No. 184 to Facility Operating License No.
DPR-42 and Amendment No. 174 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 February 28, 2007.
The amendments revise Technical Specification (TS) 5.2.2, Plant Staff, and TS 5.3, Plant Staff Qualifications, requirements for shift technical advisor (STA) qualifications. The proposed changes specify that personnel who perform the function of STA shall meet the qualification requirements of the Commission Policy Statement on Engineering Expertise on Shift, published in the Federal Register on October 28, 1985 (50 FR 43621). This change allows qualified personnel to perform the function of STA without also holding a senior reactor operator license.
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. 184 to DPR-42
- 2. Amendment No. 174 to DPR-60
- 3. Safety Evaluation cc w/encls: See next page
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: REVISE TECHNICAL SPECIFICATION 5.2.2 AND TECHNICAL SPECIFICATION 5.3 QUALIFICATION REQUIREMENTS FOR SHIFT TECHNICAL ADVISORS (TAC NOS. MD4850 AND MD4851)
Dear Mr. Wadley:
The Commission has issued the enclosed Amendment No. 184 to Facility Operating License No.
DPR-42 and Amendment No. 174 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 February 28, 2007.
The amendments revise Technical Specification (TS) 5.2.2, Plant Staff, and TS 5.3, Plant Staff Qualifications, requirements for shift technical advisor (STA) qualifications. The proposed changes specify that personnel who perform the function of STA shall meet the qualification requirements of the Commission Policy Statement on Engineering Expertise on Shift, published in the Federal Register on October 28, 1985 (50 FR 43621). This change allows qualified personnel to perform the function of STA without also holding a senior reactor operator license.
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. 184 to DPR-42
- 2. Amendment No. 174 to DPR-60
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC LPL3-1 r/f RidsNrrDorlLpl3-1 RidsNrrPMMChawla RidsNrrLATHarris RidsOGCRp RidsAcrsAcnw&mMailCenter RidsNrrDirsltsb G. Hill, OIS RidsRgn3MailCenter RidsNrrDorlDpr K. Martin N. Salgado Pk.Accession No. ML080390099 Amendment Accession No.ML080390090
- Memo from N.Salgado to C. Munson dt;11/26/07 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA IOLB:BC OGC NRR/LPL3-1/(A)BC NAME MChawla THarris N Salgado*
J Biggins PMilano DATE 02 / 25 /08 2 /12 /08 11/26/07 2 /19/08 02 / 25 /08 OFFICIAL RECORD COPY
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 184 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 28, 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. 184, 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 25, 2008
NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 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 28, 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. 174, 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, Branch 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 25, 2008
ATTACHMENT TO LICENSE AMENDMENT NOS. 184 AND 174 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 5.0-4 5.0-4 5.0-5 5.0-5
(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. 184, 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. 184
(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. 174, 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. 174
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 184 TO FACILITY OPERATING LICENSE NO. DPR-42 AND AMENDMENT NO. 174 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
In a "L-PI-07-013, License Amendment Request (LAR) to Revise Technical Specification (TS) 5.2.2 and TS 5.3 Qualification Requirements for [[Topic" contains a listed "[" character as part of the property label and has therefore been classified as invalid.s|letter dated February 28, 2007]], Nuclear Management Company (NMC) submitted a request to amend the Prairie Island Nuclear Generating Plant (PINGP) Technical Specifications (TS).
The proposed changes would revise TS Section 5.0, AAdministrative Controls,@ by relocating the qualification requirements for individuals who perform the function of shift technical advisor (STA) to the same section in the TS that the responsibilities are defined. The proposed revision will specify that STAs must fulfill the requirements as described in the Policy Statement on Engineering Expertise, that was provided by Generic Letter 86-04 (GL 86-04), dated February 13, 1986. The revision will also remove the requirement for an STA to hold a senior reactor operator (SRO) license.
2.0 REGULATORY EVALUATION
The Commission=s regulatory requirements related to the content of TS are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36. This regulation requires that the TS include items in five specific categories. These categories include: 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.
Specifically,10 CFR 50.36(d)(5) describes administrative controls as Aprovisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of each facility in a safe manner.@ The specific content of the administrative controls section of the TS is information the Commission deems essential for the safe operation of the facility that is not adequately covered by other regulations. Accordingly, the staff has determined that requirements not specifically required under 10 CFR 50.36(d)(5) and not otherwise necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety, can be removed from administrative controls.
NUREG-0737, "Clarification of TMI Action Plan Requirements," identifies those items for which TSs are required and provides guidance in the area of STA requirements. GL 86-04 offers licensees two options for meeting the current requirements for providing engineering expertise on shift (NUREG-0737, Item I.A.1.1), and meeting licensed operator staffing requirements (10 CFR 50.54 (m)(2)). Option 1 provides for elimination of the separate STA position by allowing licensees to combine one of the required SRO positions with the STA position into a
dual-role (SRO/STA) position. Option 2 states that a licensee may continue to use an Nuclear Regulatory Commission (NRC)-approved STA program while meeting licensed operator staffing requirements. Licensees may use either option on each shift.
3.0 TECHNICAL EVALUATION
Administrative (non-technical) modifications to TS are intended to incorporate human factors principles into the form and structure of TS so plant operations personnel can more easily and effectively use them. The two modifications are editorial changes to the TS, which involve reorganization and reformatting of current administrative control requirements without affecting the technical content or operational restrictions of the TS.
3.1 TS Section 5.2.2.f PINGP TS 5.2.2.f currently requires the STA to provide technical support. The proposed change will add a requirement for the STA to meet the requirements in the Commission Policy Statement as discussed in GL 86-04 to this subsection. This modification moves the qualification requirements for the STA from TS 5.3.1 to TS 5.2.2.f and also removes the requirements for the STA to hold an SRO license. This change is in accordance with the requirements in NUREG-0737, and 10 CFR 50.54(m)(2), which are referenced in GL 86-04.
NUREG-0737 requirements state that the STA shall have a bachelor's degree or equivalent in a scientific or engineering discipline and have received specific training in the response and analysis of the plant for transients and accidents. NUREG-0737 also requires the STA to receive training in plant design and layout, including the capabilities of instrumentation and controls in the control room. The STA is not required to hold an SRO as long as the licensed operator staffing requirements are met. This modification does not change the staffing requirements.
The NRC staff finds the proposed change acceptable because the editorial changes to TS 5.2.2.f retain the requirements for providing engineering expertise on shift. The removal of the requirement for the STA to hold an SRO license is also acceptable because TS 5.2.2.b and TS 5.3.2 specify the minimum staff requirements set forth in 10 CFR 50.54(m).
3.2 TS Section 5.3.1 The proposed change deletes the requirements in PINGP TS 5.3.1 regarding the qualifications for personnel who perform the STA functions. As stated in Section 3.1, TS 5.2.2.f will address the qualification requirements for the STA. This change will be made in accordance with the requirements for providing engineering expertise on shift in NUREG-0737.
The NRC staff finds the proposed change acceptable because the proposed change to TS 5.2.2.f. addresses the requirements of the Policy Statement on Engineering Expertise on Shift that is being removed from TS 5.3.1, as described in the previous section.
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 proposed amendment is confined to (i) changes to surety, insurance, and/or indemnity requirements, or (ii) changes to recordkeeping, reporting, or administrative procedures or requirements. 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 26177). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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: K. Martin Date: February 25, 2008
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 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 Michael B. Sellman President and Chief Executive Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016 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 July 2006