L-HU-08-016, Corrected Operating License Pages Regarding Transfer of Operating Authority

Corrected Operating License Pages Regarding Transfer of Operating Authority

ML082200121
Person / Time
Site:	Monticello, Prairie Island   (DPR-022, DPR-042, DPR-060, SNM-2506)
Issue date:	08/06/2008
From:	Weinkam E Nuclear Management Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-HU-08-016
Download: ML082200121 (11)

Text

Committed to Nuclear Excellence

/

August 6,2008 L-HU-08-016 10 CFR 50.80, 50.90 10 CFR 72.50, 72.56 US Nuclear Regulatory Commission Attn: Document C:ontrol Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant, Monticello Nuclear Generating Plant Units 1 and 2 Docket 50-263 Dockets 50-282 and 50-306 Renewed License No. DPR-22 License Nos. DPR--42 and DPR-60 Prairie Island Independent Spent Fuel Storage Installatior)

Docket 72-1 0 Materials License No. SNM-2506 CORRECTED OPEIRATING LICENSE PAGES FOR MONTICELLO NUCLEAR GENERATING P L i W

Reference:

NMC: to NRC letter dated April 16, 2008 "Application for Order and Conlforming License Amendments to transfer Operating Authority under Facility Operating Licenses DPR-22, DPR-42, DPR-60, and Materials Lice~nse SNM-2506".

By letter dated April 16,2008, Nuclear Management Company, LLC (NMC) and Xcel Energy submitted an application requesting the transfer of operating authority for the aforementioned licenses from NMC to Northern States Power Company-Minnesota (NSPM).

During the NRC staff review of the application, it was noted that the Monticello Nuclear Generating Plant (IMNGP) Operating License (OL) pages were not the latest version.

Via e-mail, the corrected final pages were submitted to the MNGP Project Manager.

In order to provide the NRC with the correct docketed information, Enclosure 1 contains the corrected pages hand-marked with the appropriate changes for the operating authority transfer request.

414 Nicollet Mall, MP-4 Minneapolis, MN 55401

Document Control Desk Page 2 Summaw of Commitments This letter contains no new commitments or revisions to existing commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executedon: 0 6 A t, ~ u l / *

• 5 Preparedness Nuclear Management Company, LLC

Enclosure:

1 cc:

Regional Aclministrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Generating Plant, USNRC State of Minnesota Representative

ENCLOSURE 1 Corrected Marked-up Renewed Operating License NO. DPR-22 Docket No. 50-263 Monticello Nuclear Generating Plant

FACILITY OPERATING LICENSE DPR-22 FOR MONTICELLO NUCLEAR GENERATING PLANT UNIT I MONTICELLO, MINNESOTA NORTHERN STATES POWER COMPANY DOCKET NO. 50-263

NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT, UNIT NO. I RENEWED FACILITY OPERATING LICENSE License No. DPR-22 *

1.

The Nuclear Regulatory Commission (NRC or the Commission), having previously made the findings set forth in License No. DPR-22 issued on January 9, 1981, has now found that:

A.

The application to renew operating License No. DPR-22 filed by Nuclear Management Company, LLC* (NMC) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comm~ission's rules and regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Monticello Nuclear Generating Plant, Unit No. 1 (the facility),

has been completed in conformity with Construction Permit No. CPPR-31 and the application, the provisions of the Act, and the regulations of the Commission; C.

Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functic~nality of structures and components that have been identified to require review under 10 CFR 54.21(a)(l), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasoriable assurance that the activities authorized by this renewed operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the facility, and that any changes made to the facility's current licensing basis in order to comply with 10 CFR 54.29(a) are in accordance with the Act and the Commission's regulations; D.

The facility will operate in conformity with the application, the provisions of the Act, and regulations of the Commission; E.

There is reasonable assurance: (i) that the activities authorized by this renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the

~lity and control over physi

authorized by this renewed operating license 10 CFR Chapter I; Agreements," of the Commission's regulations; i

I H.

The issuance of this renewed operating license will not be inimical to the I

commcm defense and security or to the health and safety of the public; 1

I.

After weighing the environmental, economic, technical, and other benefits of the 1

facility against environmental and other costs and considering available I

alternatives, the issuance of this renewed Facility Operating License No.

1 DPR-22, subject to the conditions for protection of the environment set forth herein, i

is in accordance with 10 CFR Part 51 (formerly Appendix D to Part 50), of the Commission's regulations and all applicable requirements have been satisfied; and 1

J.

The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this renewed operating license will be in accordance I

with the Commission's regulations in 10 CFR Parts 30, 40, and 70.

I

2.

The Facility Operating License No. DPR-22 dated January 9, 1981, is s~erseded by nse No. DPR-22, hereby issued t o & & t ~ - s

%\\*he A.

This renew ense applies to the Monticello Nuclear Generating Plant, Unit No. 1, a single cycle, forced circulation, boiling water nuclear reactor and electric generating equipment (the facility). The facility is located in Wright County on the Northern States' site in Wright and Sherburne Counties, Minnesota, and is described in the "Final Safety Analysis Report," as supplemented and amended (Amendment Nos. 9 through 28) and in its Environmental Report, as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

1.

Pursuant to Section Produc ation Facilities,"

posses at the designated location in Wright County, Minnesota, in accordance with the procedures and limitation set forth in this license;

' Northern States Power Company was incorporated in Minnesota as a wholly owned subsidiary of Xcel Energy, Inc..

effective August 18, 2000. This license, as amended, was amended effective this date to reflect the Commission's consent p6r 10 CFR Part 50, Section 50.80 to the license transfer approved by Order dated May 12, 2000.

e "

2.

Pursuant to the Act and 10 CFR Part 7 eceive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensee's filings dated August 16, 1974 (those portions dealing with han 1977 (those portions dealing with fuel

3.

Pursuant to the Act and 10 CFR Pa possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts Pursuant to the Act and 10 CFR Pa vebh

4.

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 calibration or associated with radioactive apparatus or components; and

5.

Pursuant to the Act and 10 CFR not separate, such byproduct produced by operation of the facility.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I and is sub,ject 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 to operate the facility at steady state reactor core power levels not in excess of 1775 megawatts (thermal).

2.

Technical Specifications contained in Appendix A, as r incorporated in the license.

operate the facility in accordance with the Technical Specificat~ons.

nt and maintain in effect all provisions of the ed physical security, guard training and qualification, ingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Renewed License No. DPR-22 Amendment No. 44hA+SL

.F,

Requirements revisions to 10 CFR 73.55 (51 FR 2781 7 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p)(2). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Monticello Nuclear Generating Plant Physical Security, Training and Qualification, and Safeguards Contingency Plan,"

with revisions submitted through May 12,2006.

maintain in effectall provisions of the approved as described in the Updated Safety Analysis Report for the facility and as approved in the SER dated August 29, 1979, ruary 12, 1981 and October 2, 1985, subject ke changes to the approved fire protection program without prior approval of the Commission only if those changes I

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would not adversely affect the ability to achieve and maintain safe h \\

shutdown in the event of a fire.

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5.

Emeraencv Preparedness Plan

- ~34&=&

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-hall follow and maintain in effect emergency plans which meet the standards of 10 CFR 50.47(b) and the requirements in 10 CFR 50, Appendix E, including amendments and changes made pursuant to the authority of 10 CFR 50.54(q). The licensee shall meet the requirements of 1 0 CFR 50.54(s), 50.54(t), and 50.54(u).

TMI Action Darrell G. Eisenhut, Director, Division of Licensing, Office of Nuclear Reactor Regulation to All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits (NUREG-0737).

7.

Re~airs to the Recirculation Svstem Pipinq The repairs to the recirculation system piping are approved and the unit is hereby authorized to return to power operation, subject to the following condition:

Renewed License No. DPR-22

~ m m A w e d @*. -

approval, a program for inspection and/or modification of the recirculation system piping.

8.

Additional Conditions The Additional Conditions contained in Appendix C, as revised throu h -Do\\&

Amendment No. 110, are hereby incorporated into this license. &P

,. shall operate the facility in accordance with the Additional Conditions. s v 3

9.

Implementation of New and Revised Surveil[ance Requirements AX&

For surveillance requirements that are new in Amendment No. 146, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.

For surveillance requirements that existed prior to Amendment No. 146, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For surveillance requirements that existed prior to amendment No. 146 that have modified acceptance criteria, the first performance is due at the end of the first surveillance hterval that began on the date the surveillance was last performed prioi to the implementation of this amendment.

For surveillance requirements that existed prior to Amendment No. 146, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

10.

Removed Details and Reauirements Relocated to Other Controlled Documents License Amendment No. 146 authorizes the relocation of certain technical specifications to other licensee-controlled documents.

Implementation of this amendment shall include relocation of these requirements to the specified documents, as described in (1) Section 5.0 of the NRC staff's Safety Evaluation, and (2) Table LA, Removed Detail Changes, and Table R, Relocated Specifications, attached to the NRC staff's Safety Evaluation.

11.

Mitiqation Strateqv License Condition

?

Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

c,

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets 0

I I

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders

12.

The licensee shall implement and maintain all Actions required by hall have and maintain financial protection of the Commission shall require in accordance G.

The Updated Safety Analysis Report supplement; as revised, submitted pursuant to 10 CFR 54.21 (d), shall be included in the next scheduled update to the Updated Safety Analysis Report requir issuarlce of this renewed operating lic requirements in that section.

t, as revised, describes c future activities to be completed prior to the period of extended operation.

shall c:omplete these activities no later than September 8, 201 0, and shall the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

w -

I.

All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of the most recent NRC-approved version of the Boiling Water Reactor Vessels and lntemals Project (BWRVIP)

Integrated Surveillance Program (ISP) appropriate for the configuration of the specimens in the capsule. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.

J.

This renewed operating license is effective as of the date of issuance and shall expire at midnight, September 8, 2030.

FOR THE NUCLEAR REGULATORY COMMISSION IRN J. E. Dyer, Director Office of Nuclear Reactor Regulation Attachments: 1. Appendix A - Technical Specifications

2. Appendix 8 - (Deleted. per Amendment 15, 12/17/82)

3. Appendix C - Additional Conditions Date of Issuance: N~ovember 08, 2006 Renewed License No. DPR-22