ML19305E136

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Mod of 791130 Order Deleting & Replacing Condition 1 of Section Iv.Testing Must Be Performed within 90 Effective Full Power Days.Health & Safety Will Not Be Endangered by Order Remaining in Effect.Safety Evaluation Encl
ML19305E136
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 04/04/1980
From: Case E
Office of Nuclear Reactor Regulation
To:
WISCONSIN ELECTRIC POWER CO.
Shared Package
ML19305E133 List:
References
NUDOCS 8004230014
Download: ML19305E136 (5)


Text

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION i

In the Matter of

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WISCONSIN ELECTRIC P0',iER C0!9ANY

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Docket No. 50-266 (Point Beach Nuclear Plant, Unit 1)

MODIFICATION OF NOVEMBER 30, 1979 ORDER I.

Wisconsin Electric Power Company (the licensee) is the holder of l

Facility Operating License No. DPR-24 which authorizes the licensee to operate the Point Beach Nuclear Plant, Unit 1, located in Two Creeks, Wisconsin, under certain specified conditions.

License No. DPR-24 was issued by the Atomic Energy Cormission on October 5,1970 and is due to expire on July T5, 2008.

II.

1 Inservice inspections of the Point Beach Unit 1 steam generators performed during the August 1979 and October 1979 outages indicated extensive general intergranular attack and caustic stress corrosion cracking on certain of the external surfaces of the steam generator tubes.

As a result of information provided in discussions with the licensee and its representatives, which is documented in a letter dated November 23, 1979 from S. Burstein to H. R. Denton, and the Staff's Safety Evaluation Report, dated November 30, 1979, on Point Beach Unit 1, Steam

. Generator Tube Degradaticn due to Deep Crevice Corrosion, it was determined that additional operating conditions would be required to assure safe oper-ation prior to resumption of operation of Unit 1 from the 1979 refueling outage.

III.

The licensee in letters dated November 29, 1979 and November 30, 1979 agreed to additional conditions which were necessary to provide reascnable assurance for safe operation of Unit 1.

On November 30, 1979, an Order was issued to impose limiting conditions on continued operation of Unit 1 for a period of 60 effective full power days, at which time the licensee was required to shut down until the Director of Nuclear Reactor Regulation determined in writing in accordance with condition 6 of the Order that the results of the eddy current tests required by the Order were acceptable.

On February 28,1980, Unit I was taken out of service for the tests required by the Order.

On March 28,1980, the licensee provided the results of such tests to the NRC.

In accordance with condition 6 of the November 30, 1979 Order the NRC staff has reviewed the licensee's March 28, 1980 submittal and has assessed whether continued operation of the facility would be safe.

I have found for the reasons given in the attached Safety Evaluation that the public health, safety and interest requires that Unit 1 be shut down and certain tests be conducted within 90 effective full power days of operation after the date of this Order.

The licensee has agreed to this condition.

Subject to this condition and with continuation cf the other conditions set forth in the November 30, 1979 Confirmatory Orcer and the January 3,1980 !<odification of the Order, I have concluded that there is reasonable assurance that the public health and safety will not be endangered by the continued operation of Point Beach Unit 1.

IV.

Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Commission's Rules and Regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED THAT the November 30, 1979 Confirmatory Order for Modification of License be amended, effective immediately, to delete condition 1 of Section I'/ of that Order and replace such condition with the folicwing condition.

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1.

Within 90 effective full power days from the date of this Order, a 2000 psia primary-to-secondary hydrostatic test I

and a 800 psia secondary-to-primary hydrostatic test shall i

be performed.

Also during this plant outage, an eddy i

current examination shall be performed on tubes in each j

steam generator.

The program shall be submitted to the NRC for staff review and require examination cf about 1000 tubes in the. central region of the hot leg and three (3) percent of all tubes outside this central region and 3% of all cold leg tubes.

The central region shall encompass all areas where deep crevice corrosion has previously been observed.

. A ::her conditi:ns cf the November 30, 1979 Confirmatory Order and the Ja.uiry 3,1980 modification of that Order, including condition 6 requiring that the licensee not resume operation after the required eddy current examinations until the Director, Office of Nuclear Reactor Regulation, ce ermines in writing that the results of such tests are acceptable,

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remain in effect in accordance with their terms.

1 V.

Copies of the above referenced documents are available for inspection at the Commission's Public Document Room at 1717 H Street, N.W., Washington, D. C. 20555, and are being placed in the Commission's local public document ccor at the Document Department, University of Wisconsin, Steven's Point 4

Library, Stevens Point, Wisconsin 54451.

VI.

Any person whose interest may be affected by this Order may within twenty days of the date of this Order request a hearing with respect tc this Order. Any recuest for a hearing shall be addressed to the Director of Suclear. Reactor Regulation, U. S. Nuclear Regulatory Commission, Washington, D. C.

20555 with a copy to the Executive Legal Director at the above address.

If a hearing is requested by a person who has an interest affected by the order, the Commission will issue an order designating the time and place of nearing.

Any such request SHALL NOT STAY THE IMMEDI ATE EFFECTIVENESS CF THIS OR3ER.

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! In the event a hearing is held, the issues to be considered at such hearing shall be:

1.

Whether the facts stated.in Sections II and III of this Order provide an adequate basis for actions ordered; and 2.

Whether the license should be modified to include the conditions 1

set forth in Part IV of this Order.

FOR THE NUCLEAR REGULATORY COMMISSION 5s

./ Edson G. Case, Acting Director

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Office of Nuclear ' Reactor Regulation

Attachment:

Staff Safety Evaluation Report

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dated April 4,1980 f

Effective Date: April 4,1980 Bethesda, Maryland i

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