ML19320D421

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Order Modifying OL Immediately,By Adding Section 6.3.2 to Tech Spec 6.3 Re Facility Staff Qualifications.Request for Hearing May Be Submitted within 25 Days
ML19320D421
Person / Time
Site: Oyster Creek
Issue date: 07/08/1980
From: Stello V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:
Shared Package
ML19320D366 List:
References
EA-80-039, EA-80-39, NUDOCS 8007210343
Download: ML19320D421 (5)


Text

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of

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Docket No. 50-219 Jersey Central Power and Light Company )

EA-80-39 (0yster Creek Nuclear Generating

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Station, Unit No. 1)

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ORDER MODIFYING LICENSE EFFECTIVE IMMEDIATELY I

The Jersey Central Power and Light Company (the " licensee") is the holde.of Operating License DPR-16 (the " license") which authorizes operation of the Oyster Creek Nuclear Generating Station at steady state reactor core power levels not in excess of 1930 megawatts thermal (rated power).

The license was issued.on April 9, 1969.

The facility consists of a boiling water moderated and cooled reactor (BWR), located at the licensee's site in Ocean County, New Jersey, nine miles south of Toms River, New Jersey.

II i

During an inspection conducted March 18 and 19, 1980 it was determined that one of.the major factors contributing to an incident involving a breakdown in radia-tion protection controls was the use of a technically unqualified technician to provide radiation' protection coveragr during the servicing pf a heavily contam-inated reactor control r.od blade handling tool.

The incident involved exposure to airborne radioactive material which resulted in an intake by one of the workers of approximately 29 percent of the 10 CFR 20 Appendix B quarterly i

8007210343-

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limit of cobalt 60.

A second instance of the use of unqualified personnel was identified during a Health Physics Appraisal inspection conducted May 12-16, 1980.

During this inspection, an unqualified contractor technician was

. observed to allow personnel to exit a work area, used for repair of heavily contaminated control rod drive mechanisms, without performing whole body frisking.

This individual was at times directly responsible for monitoring the radiological safety of the workers rebuilding the control rod drive mechanisms.

As a result of the first instance, Jersey Central Power and Light Company sent

a. letter dated April 2, 1980, to the Director, Region I, U.S.N.R.C..

In this letter, the licensee's Manager of Nuclear Generation addressed immediate corrective actions and, among other things, stated, that by April 7, 1980, Oyster Creek will use in responsible positions only radiation protection i

technicians who meet or exceed ANSI N18.1-1971.

Duties of techn.icians in responsible positions. included authorization to sign radiation work permits and, independently _ perform surveys and evaluations used to insure compliance with regulatory requirements.

In addition,- the letter stated tnat unqualified 4

' technicians acting in less responsible positions will be closely supervised.

As a result of the second instance and as a result of the normal inspection review process,-it was Getermined on May 16, 1980, contrary to the licensee's statement of April 7, 19'80, that the licensee was utilizing ccntractor supplied radiation protection techniciant in responsible positions who did not meet the requirements of ANSI N18.1-1971.

This NRC sampling of resumes, observation of

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,. field performance ar~ questioning indicated 4 of 28 contractor technicians did not met; ANSI N18.1-1971 requirements.

Of the 4, 2 were determined to have no prior applied neclear power plant experience.

It was later determined by the licensee that an additional 10 of the 28 contractor technicians did not meet the ANSI N18.1 requirements.

The above findings indicate that the licensee has not adopted appropriate controls to assure the utilization of only qualified technicians in activities important to the protection of workers.

I have determined that the public health, safety and interest require modification of License No. OPR-16 as stated in Part III of this Order, effective immediately.

III Acco,rdingly, pursuant to the Atomic Energy Act of 1954, as amended, and the i

Commission's regulations in 10 CFR Parts 2 and 50, License No. DPR-16 is modi-

.fied effective immediately by the following addition to Technical Specification 6.3, Facility Staff Qualifications:

6.3.2 Each member of the radiation protection organization for which there is a comparable pos'ition described in ANSI N18.1-1971 shall meet.or exceed

-the minimum qualifications specified therein, or in -the case of. radiation protection technicians, they shall have at least one year's continuous

4 experience in appl.ied radiation protection work in a nuclear facility dealing with radiological p 'blems similar to those encountered in nuclear

-power stations, and shall have been certified by the Supervisor, Radiation Protection (RPM), 6s qualified to perform assigned functions.

This certification must be based on an NRC approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by responsible supervis. ion that the individual has demonstrated his ability to perform each specified procedure and assigned function with an understanding of its basis and purpose.

1 IV' The licensee, or any other person who has an interest affected by this Order may,:within twenty-five days of the date of this Order, request a hearing.

A request for a hearing shall be addressed to the Secretary to the Commission, U.S.N.R.C., Washington, D.C 20555.

A copy of the hearing request shall also be spnt to the Executive Legal Director U.S.N.R.C., Washington, D.C.

20555.

If a hearing is requested by the-licensee or an interested person, the Commission will issue an Order designating the time and place of hearing.

Such a request for hearing SHALL NOT STAY-THE IMMEDIATE EFFECTIVENESS OF THIS ORDER.

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, l V

In the event the licensee or any other interested person requests a hearing as provided above and a hearing is held, the issues to be considered at such a hearing shall be:

(1) whether the. facts set forth in Part II of this Order.are correct; and,

-(2) whether this Order should be sustained.

FOR THE NUCLEAR REGULATORY COMMISSION 4\\

Victor Stello, Jr.

Director Office of Inspection and Enforcement Dated gt Bethesda, Maryland this. 5 day of ITbjb4, 1980 3

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