Information Notice 1988-78, Implementation of Revised NRC-Administered Requalification Examinations

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Implementation of Revised NRC-Administered Requalification Examinations
ML031150081
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, 05000310, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane
Issue date: 09/22/1988
From: Rossi C
Office of Nuclear Reactor Regulation
To:
References
IN-88-078, NUDOCS 8809190047
Download: ML031150081 (5)


I

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C.

20555

September 22, 1988

NRC INFORMATION NOTICE NO. 88-78:

IMPLEMENTATION OF REVISED NRC-ADMINISTERED

REQUALIFICATION EXAMINATIONS

Addressees

All holders of operating licenses or construction permits for nuclear power

reactors.

Purpose

This information notice is being provided to inform addressees of the NRC

staff's intention to implement a revised requalification examination program

beginning in October 1988. It is expected that recipients will review the

information for applicability to their facilities and consider actions, as

appropriate. However, suggestions contained in this information notice do

not constitute NRC requirements; therefore, no specific action or written

response is required.

Background

The regulation 10 CFR Part 55, which became effective on May 26, 1987, pro- mulgated a requirement that each holder of an operator's license in a nuclear

power facility pass "a comprehensive requalification written examination and

operating test administered by the Commission during the term of a six-year

license." The initial program to implement this regulation experienced dif- ficulty because of a number of deficiencies that were made known to the NRC

staff. In September 1987, the staff suspended all NRC-administered requali- fication examinations to evaluate the feedback received from the field and

to consider appropriate revisions to the program. The program now has been

revised and field tested at one site in each of the five regions. Having in- corporated corrections of the known deficiencies of the previous program and

also the lessons from field testing at the five sites, full-scale resumption

of the NRC-administered requalification examination will begin in October 1988.

Discussion:

The requalification examinations conducted by the NRC will consist of the

following:

1. Operating Test

a. Crew Evaluations:

Evaluations of crew performance will be performed

in the simulator.

Individual operator weaknesses will be flagged for

followup evaluation during the plant walkthrough.

08809S190047

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-1 IN 88-78 September 22, 1988 b.

Individual Evaluations:

The NRC will observe plant walkthroughs

during which operators will be expected to successfully implement

job performance measures for selected tasks. Operators also will

be expected to demonstrate understanding of the job performance

measures by satisfactorily answering performance-based questions

related to the tasks.

2. Written Examination

The written examination will be administered in an open-reference format, which allows the use of available reference. materials, and will consist

of the following two sections:

a.

Plant Operations: This section will be administered in a simulator

or an equivalent device. Questions will be based on the status of

the "frozen" simulator (or the equivalent device). The operator will

be able to refer to simulator indications and reference materials

present in the simulator in responding to test questions.

b. Limits and Controls: This section will be conducted in a simulator

or a classroom.

Questions will be asked about plant procedures and

administrative controls. A complete set of reference materials used

-

-to-operatethe-plant will be ava1lableduring-the-writte.rexaminatjon.

Before the examination is administered, all aspects of the examination will be

reviewed by facility representatives to ensure that examination questions, scenarios, and job performance measures are performance based and technically

correct. This revised process will result in an examination that accurately

reflects the ability of operators to satisfactorily perform licensed duties.

The staff fully intends to continue to improve the process on the basis of the

feedback received so as to maximize operational safety.

Addressees

may wish to

provide a copy of this information notice to each licensed operator and senior

operator at their facilities.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

L. A. Wiens, NRR

(301) 492-3171 Attachment: List of Recently Issued NRC Information Notices

Attachment

IN 88-78 September 22, 1988 LIST OF RECENTLY'ISSUED

NRC INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issuance

Issued to

88-77

88-76

88-75

88-74

88-73

88-72

Inadvertent Reactor

Vessel Overfill

Recent Discovery of a

Phenomenon not Previously

Considered in the Design

of Secondary Containment

Pressure Control

Disabling of Diesel

Generator Output Circuit

Breakers by Anti-Pump

Circuitry

Potentially Inadequate

Performance of ECCS in

PWRs During Recirculation

Operation Following a LOCA

Direction-Dependent Leak

Characteristics of

Containment Purge Valves

Inadequacies in the Design

of dc Motor-Operated Valves

Possible Environmental

Effect of the Reentry

of COSMOS 1900 and

Request for Collection

of Licensee Radioactivity

Measurements Attributed

to That Event

Check Valve Inservice

Testing Program

Deficiencies

Movable Contact Finger

Binding in HFA Relays

Manufactured by General

Electric (GE)

9/22/88

9/19/88

9/16/88

9/14/88

9/8/88

9/2/88

9/1/88

8/29/88

8/19/88

All holders of OLs

or CPs for BWRs.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for W and

,-B&W-destgneU

nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors, fuel

cycle licensees, and Priority 1 material licensees.

All holders of OLs

or CPs for nuclear

power reactors.

All holders of OLs

or CPs for nuclear

power reactors.

88-71

88-70

88-69 OL = Operating License

CP = Construction Permit

IN 88-78 September 22, 1988 b. Individual Evaluations:

The NRC will observe plant walkthroughs

during which operators will be expected to successfully implement

job performance measures for selected tasks.

Operators also will

be expected to demonstrate understanding of the job performance

measures by satisfactorily answering performance-based questions

related to the tasks.

2. Written Examination

The written examination will be administered in an open-reference format, which allows the use of available reference materials, and will consist

of the following two sections:

a. Plant Operations:

This section will be administered in a simulator

or an equivalent device. Questions will be based on the status of

the "frozen" simulator (or the equivalent device). The operator will

be able to refer to simulator indications and reference materials

present in the simulator in responding to test questions.

b. Limits and Controls: This section will be conducted in a simulator

or a classroom. Questions will be asked about plant procedures and

administrative controls. A complete set of reference materials used

to operate the plant will be available during the written examination.

Before the examination is administered, all aspects of the examination will be

reviewed by facility representatives to ensure that examination questions, scenarios, and job performance measures are performance based and technically

correct.

This revised process will result in an examination that accurately

reflects the ability of operators to satisfactorily perform licensed duties.

The staff fully intends to continue to improve the process on the basis of the

feedback received so as to maximize operational safety.

Addressees

may wish to

provide a copy of this information notice to each licensed operator and senior

operator at their facilities.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

L. A. Wiens, NRR

(301) 492-3171 Attachment: List of Recently Issued NRC Information Notices

  • SEE PREVIOUS CONCURRENCES

C/OGCB:DOEA:NRR

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09/08/88

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IN 88- September xx, 1988 b.

Individual Evaluations: NRC will observe plant walkthroughs during

which operators will be expected to successfully implement job

performance measures for selected tasks.

Operators also will be

expected to demonstrate understanding of the Job performance measures

by satisfactorily answering performance-based questions related to

the tasks.

2. Written Examination

The written examination will be administered in an open-reference format, which allows the use of available reference materials, and will consist of

the following two sections:

a. Plant Operations: This section will be administered in a simulator

or an equivalent device. Questions will be based on the status of

the "frozen" simulator (or the equivalent device).

The operator will

be able to refer to simulator indications and reference materials

present in the simulator in responding to test questions.

b. Limits and Controls:

This section will be conducted in a simulator

or a classroom.

Questions will be asked about plant procedures and

administrative controls. A complete set of reference materials used

to operate the plant will be available during the written

examination.

Before the examination is administered, all aspects of the examination will be

reviewed by facility representatives to ensure that examination questions, scenarios, and job performance measures are performance based and technically

correct.

This revised process will result in an examination that accurately

reflects the ability of operators to satisfactorily perform licensed duties.

The staff fully intends to continue to improve the process on the basis of the

feedback received so as to maximize operational safety. The staff suggests

that a copy of this information notice be provided to each licensed operator

and senior operator at each facility.

No specific action or written response is required by this information notice.

If you have any questions about this matter, please contact the technical

contact listed below or the Regional Administrator of the appropriate regional

office.

Charles E. Rossi, Director

Division of Operational Events Assessment

Office of Nuclear Reactor Regulation

Technical Contact:

L. A. Wiens, NRR

(301) 492-3171 Attachment:

List of Recently Issued NRC Information Notices

44M

  • SEE PREVIOUS CONCURRENCES

D/DOEA:NRR

C/O 9:DOEA:NRR

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