ML20153H598

Application for Amends to Licenses DPR-42 & DPR-60,revising Expiration Date of Unit 1 OL to 130809 & Unit 2 OL to 141029

ML20153H598
Person / Time
Site:	Prairie Island
Issue date:	02/21/1986
From:	Musolf D NORTHERN STATES POWER CO.
To:
Shared Package
ML20153H587	List: ML20153H584 ML20153H598 ML20153H602
References
NUDOCS 8603030228
Download: ML20153H598 (7)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 AND DPR-60 LICENSE AMENDMENT REQUEST DATED FEBRUARY 21, 1986 Northern States Power Company, a Minnesota corporation, requests authorization for changes to the Prairie Island Operating Licenses as shown on the attachments labeled Exhibit A and Exhi-bit B. Exhibit A describes the proposed changes along with reasons for the changes. Exhibit B contains copies of the Prairie Island Operating Licenses incorporating the proposed changes.

This letter contains no restricted or other defense infor-mation.

NORTHERN STATES POWER COMPANY By O Uw s David Musolf Manager-Nuclear Supp t Services On this plat' day of h, /984 before me a notary public in and for said(Dounty, personally appeared David Musolf, Manager-Nuclear Support Services, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, informa-tion, and belief the statements made in it are true and that is is not interposed for delay.

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Exhibit A Prairie Island Nuclear Generating Plant 4

License Amendment Request Datid February 21, 1986 Description and Evaluation of Proposed Change to Operating Licenses DPR-42 and DPR-60 Pursuant to 10 CFR Part 50, Section 50.90, the holders of Opera-ting Licenses DPR-42 and DPR-60 hereby propose the following changes:

License Expiration Date

a. Change paragraph 2.D of the Facility Operating License for-Unit No. 1 of the Prairie Island Nuclear Generating Plant, License No.

DPR-42, to read:

D. This amended license is effective as of the date-of issuance and shall expire at midnight August 9, 2013.

b. Change paragraph 2.D of the Facility Operating License for Unit No. 2 of the Prairie Island Nuclear Generating Plant, License No.

DPR-60, to read:

D. This amended license is effective as of.the date of

, issuance and shall expire at midnight October 29, 2014.

Refer to Exhibit B for the actual page changes, i Reasons for Change The current Operating License expiration date is 40 years from the date of issuance of the Construction Permit (June 25, 1968 for both units). Because approximately 61 months were required to construct Unit No. 1 to the point of fuel loading and startup testing (76 months for Unit No. 2), the effective period of the Unit No. I license is approximately 34 years and 11 months'(33 years and eight months for Unit No. 2). Current NRC policy is to issue operating licenses for a 40-year period beginning with the date of issuance. The requested change in expiration date of the Prairie Island Operating Licenses _would provide for the 40-year period of operation that the units were initially designed for.

Northern States Power Company believes that the useful life of Prairie Island Unit No. I and Unit No. 2 is significantly more than the 40 years requested in this license amendment applica-tion. We are currently involved in a Plant Life Extension Prog-J m.m , , e ._. _ -..--,.m - ,y yy, -

EXHIBIT A Reasons for Change (continued) ram (PLEX) pilot project at our Monticello Nuclear Generating Plant. This program is being supported by the Electric Power Research Institute (EPRI) and the US Department of Energy (DOE).

The purpose of this program is to determine the optimum eafe operating life of the facility and establish a program of sur-veillance, testing, and planned replacement / refurbishment to support this goal. A similar PLEX pilot project is under way for Virgina Power Corporation's Surrey Unit ho. 1, which is a Westinghouse pressurized water reactor plant similmc in many respects to the Prairie Island Units. We are actively following both pilot projects and have plans to initiate a plant specific plant life extension program at Prairie Island in 1987.

Determination of Significant Hazards Consideraticus The proposed change to the operating License has been evaluated to determine whether it constitutes a significant hazards consid-eration as required by 10 CFR Part 50, Sections 50.91 using the standards provided in Section 50.92. This analysis is provided below:

1. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.

Prairie Island Unit No. I and Unit No. I were designed and constructed primarily on the basis of 40 years of plant operation. For example, the reactor vessel was designed and fabricated for a 40-year life. A comprehensive vessel ma-terials surveillance program is maintained in accordance j with 10 CFR Part 50, Appendix H. Analyses performed to demonstrate compliance with the NRC pressurized thermal shock screening criteria indicate that approximately 80 years of plant operation is possible prior to reaching a limit.

The analyses contained in the Prairie Island Final Safety Analysis Report were performed primarily on the basis of 40 years of plant operation.

Analyses and information presented in the Prairie Island Environmental Report, in general, were not dependent on any specific period of plant operation.

EXHIBIT A

~3-Determination of Signi ficant Hazards Considerations (continued)

Procedures and programs are in place to detect abnormal deterioration and aging of critical plant components.

Examples include:

a. Plant pressure retaining vessels, piping, and sup-port systems are inspected in accordance with Section XI of the-ASME Boiler and Pressure Vessel Code and 10 CFR~Part 50, Section 50.55(g). Safety related pumps and valves are included in a test program meeting the requirements of Section XI of the Code and the plant Technical Specifications.

b. Safety related electrical equipment has been en-vironmentally qualified in accordance with the require-ments of 10 CFR Part 50, Section 50.49. Aging analyses establish required intervals for equipment replacement.

c. A number of special inspections and investigations have been performed by the Prairie Island technical staff providing additional assurance that abnormal or unanticipated degradation will not occurring in compo-nents required for safe and reliable plant operation.

These inspections have included such items as pipe, valve, and fitting wail thickness measurements in steam lines subject to erosien. Additional inspections of this nature will be ideatified as part of the Prairie Island plant specific PLEX program.

2. The proposed amendment will not create the possibility of-a new or different kind of accident from any accident previously analyzed.

The proposed amendments involve only a change in the expira-tion date of the Operating Licenses. No safety analyses are affected. No new or different accident type is created. The accident analyses presented in the Updated Safety Analysis Report remain bounding.

3. The proposed amendment will not involve a significant reduction in the margin or safety.

The proposed amendment involves only a change in the expira-tion dates of the Operating Licenses. No safety margins are affected.

f EXHIBIT A The licensing basis of the plant, as described in the Up-dated Safety Analysis Report and the Environmental report, are applicable for 40 years of plant operation.

For the reasons stated above, we have concluded that these li-cense amendments doe not involve a significant hazards considera-tion. They consist of purely administrative changes in the term of the operating Licenses hich is permitted by the regulations of the Commission.

Review of Prairie Island Environmental Report We ~have reviewed the Prairie Island Environmental Report dated May 12, 1971 as supplemented on November 5, 1971. We have con-cluded that the environmental impact associated with operation of the Prairie Island Unit No. I and Unit No. 2 for a 40 year period of operation was considered in this report.

~

The Environmental Report, as supplemented, does not generally use or discuss a specific period of plant operation in the evaluations presented.

In the approximately 15 years of plant operation since the Envi-ronmental Report was issued, a number of modifications have been made to the Prairie Island plant and surrounding site and facili-ties. These modifications, in general, had the effect of impro-ving the reliability and safety of the plant or reducing the environmental impact of plant operation. They include:

a. Facilities - Many modifications to the plant have been made since the original operating license has been issued.

Significant modifications are described in the Prairie Island Updated Safety Analysis Report. Modifications made without prior NRC approval in accordance with the provisions of 10 CFR Part 50, Section 50.59, were reported on an annual basis to the Commission. Modifications requiring prior NRC appro-val were made following receipt of and NRC Safety Evaluation Report. No modification was found to affect the conclusions of the Prairie Island Environmental Report.

b. Land Use - Additional site buildings have been constructed and existing buildings have been expanded. The actual land area occupied by site buildings has not significantly in-creased, however.

EXHIBIT A

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c. Thermal Effects - Modifications to the plant intake and and discharge structures have been made to further reduce the potential for adverse impact on aquatic life near the plant.

d. Radiological Effects and Radwaste Treatment Systems -

Releases of radioactive liquid and gaseous wastes from the plant remain among the lowest of US nuclear generating plants. Volume of solid wastes shipped from the' site are among the lowest of US nuclear generating plants. Computed offsite doses are typically less than one percent of the 10 CFR Part 50, Appendix I, guidelines of 10 mrad / year gamma and 20 mrad / year beta air dose and 15 mrem / year organ dose.

Occupational radiation exposure at the Prairie Island plant remains among the lowest of US nuclear generating plants.

This is attributed to an excellent history of fuel integrity, a management commitment to as low as reasonably achievable exposures, and an experietaced and motivated radiation protec-tion aupport group.

We expect that ineignificant radwaste system releases and extremely low occupational exposures will continue to be the norm for the life of the Prairie Island facility.

e. Area Population - While the plant site itself is within the City of Red Wing hinnesota, the land use in the immediate vicinity of the plant continues to be largely rural and is expected to remain so for the life of the facility. The total population within the ten-mile emergency planning zone remains relatively small.

EXHIBIT B License Amendment Request Dated February 21, 1986 Docket Nos. 50-282 License Nos. DPH-42 50-306 DPH-60 Exhibii B consicts of revised pages for the Prairie Island Unit No. I and Unit No. 2 Operating Licenses showing the proposed changes.

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