Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty

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Performance of NRC-Licensed Individuals While on Duty
ML031180229
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane
Issue date: 07/12/1985
From: Taylor J
NRC/OE, NRC/OI
To:
References
IN-85-053, NUDOCS 8507110094
Download: ML031180229 (7)


SSINS No.:

6835 IN 85-53

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D. C. 20555

July 12, 1985

IE INFORMATION NOTICE NO. 85-53:

PERFORMANCE OF NRC-LICENSED INDIVIDUALS

WHILE ON DUTY

Addressees

All nuclear power reactor facilities holding an operating license (OL) or a

construction permit (CP).

Purpose

In February 1981, the attached IE Circular 81-02 was issued. This Circular, which was prompted by an NRC inspector's observation of two licensed reactor

operators who appeared to be asleep while on duty in the control room, provided

guidance on conditions and practices which the NRC believes to be necessary

for the maintenance of a professional atmosphere in the control room and through- out the facility. The purpose of this information notice is to reaffirm the

general principles of control room operations which were provided over four

years ago.

While some of the regulatory references cited in the Circular may

have been modified or updated since that time, the basic standards of control

room professionalism remain valid as critical elements for continued safe

reactor operations.

Description of Circumstances

Continuing observation of control room operation by NRC inspectors indicates

that, in general, the high standards of control room professionalism described

in IE Circular 81-02 are being met at most facilities. Nevertheless, recent

NRC observations at some operating facilities indicate the need for further

management attention to one of the areas described in the Circular:

"Potentially distracting activities in the control room and other

watch stations must be prohibited (for example: radios, TV,

alcohol use or drug abuse, games, horseplay, hobbies, and

reading that is not directly job related)."

In some facility control rooms, NRC inspectors have observed that the playing

of music and operator occupation with reading material that is not job related

continues to be condoned by management. Many utilities have established and

are enforcing a policy which prohibits such activities by on-shift personnel.

Such activities can potentially distract the on-shift personnel from the

performance of their duties and from the monitoring of plant operations and

8507110094

IN 85-53 July 12, 1985 status. It is expected that recipients will review the information in this

notice and the attached Circular for applicability to their facilities and

consider action, if appropriate, to ensure the highest standards of control

room operations.

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

If there are any questions regarding this matter, please contact the Regional

Administrator of the appropriate NRC regional office or this office.

Director

ie of In ection and Enforcement

Technical Contact:

J. G. Partlow, IE

301-492-4614 Attachments:

1. IE Circular 81-02

2.

List of Recently Issued IE Information Notices

Attachment 1

IN 85153

8 SSINS No.:

6830 Accession No.:

Page

of

48008220282 IEC 81-02

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

WASHINGTON, D.C. 20555

February 9, 1981

I

IE Circular No. 81-02:

PERFORMANCE OF NRC-LICENSED INDIVIDUALS WHILE ON

DUTY

Description of Circumstances

Recently, an NRC inspector observed two licensed reactor operators who

appeared to be asleep while on duty in the control room.

A subsequent NRC

investigation into the matter concluded that the operators were not fully

attentive to their licensed duties of monitoring reactor conditions, which

is a serious matter of safety significance.

Furthermore, the investigation

concluded that management controls were inadequate to assure the alertness

of licensed operators while on duty.

Enforcement action was taken after

it was determined that attentive operators were not present at the controls

as required by 10 CFR 50.54(k).

Discussion:

NRC believes that a relationship exists between the professional attitude of

a nuclear plant's operating and management personnel and the degree to which

the health and safety of the public is protected.

NRC believes that

professional attitude is reflected in high standards of performance including

pride in the facility as demonstrated by the nuclear power plant staff.

Factors making up this professional attitude include knowledge of all aspects

of plant status by licensed control room operators, maintaining an orderly and

clean working environment, aggressiveness of the operating staff to prevent

operational problems, and correcting observed deficiencies.

NRC believes that

clarification of its position on this subject is necessary because several

recent events involving licensed operators indicate a lack of a professional

attitude at some nuclear power plants.

The following conditions and practices are among those the NRC believes to

be necessary for the maintenance of a professional atmosphere in the

control room and throughout the facility.

1. All on-duty NRC-licensed operators and operating supervisors must be

aware of and responsible for the plant status at all times.

This

includes supervisors being responsible for the performance of all

personnel assigned to their shift who could affect plant safety, regardless' of specialty affiliation.

Knowledge of the plant's

status must be assured during shift changes by a formal watch

turnover and relief.

Attachment:

Recently issued IE circulars

Attachment 1 IEC 81-02 IN 85-53

February 9, 1981

July 12, 1985 2. All on-duty NRC-licensed operators must be alert, remain within their

immediate areas of responsibility until properly relieved, and be

particularly attentive to the instrumentation and controls located

within these areas at all times.

3. Potentially distracting activities in the control room and other watch

stations must be prohibited (for example:

radios, TV, alcohol use or

drug abuse, games, horseplay, hobbies, and reading that is not directly

job related).

4. Control room access must be limited to those persons on official

business only and loitering in this area must be prohibited.

5. All necessary plant-related technical/administrative control room

business must be conducted at a location and in such a manner that

neither licensed control room operator attentiveness nor the professional

atmosphere will be compromised.

This includes activities associated with

the use of special eating and training facilities for on-shift personnel.

Additional Information:

NRC inspectors will be particularly mindful of those conditions and practices

described above during future inspections of licensed nuclear facilities.

For more specific information, you are referred to the following NRC documents:

1. 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities,"

Paragraph 50.54

2. 10 CFR 55, "Operators' Licenses," Paragraph 55.31 and 55.40

3. Regulatory Guide 1.114, "Guidance on Being Operator at the Controls

of a Nuclear Power Plant"

4. IE Information Notice 79-20, Revision 1, "NRC Enforcement Policy -

NRC-Licensed Individuals"

5. Letter from D. G. Eisenhut, NRC, to All Licensees and Applicants, dated July 31, 1980, Subject:

Interim Criteria for Shift Staffing

The following excerpts are taken from some of these documents and are

provided for your information:

1. Only licensed operators are permitted to manipulate the controls

that directly affect the reactivity or power level of a reactor

[10 CFR 50.54(i)].

2. Licensed operators are required to be present at the controls at all

times during the operation of the facility [10 CFR 50.54(k)].

3. Operation of mechanisms and apparatus other than controls that may

indirectly affect the power level or reactivity of a reactor shall

oKly be accomplished with the knowledge and consent of an operator

licensed in accordance with Part 55 [10 CFR 50.54(j)].

Attachment 1 IEC 81-02 IN 85-53

February 9, 1981

July 12, 1985 4. The NRC-licensed individual shall observe all applicable rules, regulations and orders of the Commission, whether or not stated

in the license [10 CFR 55.31(d)].

5. The operating test, to the extent applicable to the facility, requires the applicant to demonstrate an understanding of:

The necessity for a careful approach to the responsibility

associated with the safe operation of the facility

[10 CFR 55.23(1)).

6. In order for the operator at the controls of a nuclear power plant

to be able to carry out these and other responsibilities in a timely

fashion, he must give his attention to the condition of the plant

at all times.

He must be alert to ensure that the plant is operating

safely aid must be capable of taking action to prevent any progress

toward a condition that might be unsafe (Regulatory Guide 1.114.B).

NRC policy regarding responsibility for safe operation of NRC-licensed

facilities as stated in IE Information Notice 79-20, Revision 1, continues

to be as follows:

1. "The facility licensee is responsible for assuring that the facility

is operated safely and within the requirements of the license, technical specifications, rules, regulations, and Orders of the NRC,

and for the actions of their on-duty employees while on site."

2. "NRC-licensed individuals are responsible for taking timely and proper

actions that will not create or cause a hazard to 'safe operation of

the facility' (i.e., actions or activities, including failure to take

action, related to the facility that could have an adverse effect on

the health and safety of the public, plant workers, or the individuals)."

Recommended Action for Licensee's Consideration:

Each power reactor licensee should review and revise, as necessary, their

administrative controls regarding operator performance to ensure the guidance

contained or referenced herein is incorporated.

These administrative controls

should prescribe performance requirements for licensed personnel and specify

types of activities that are prohibited while licensed personnel are on duty.

These administrative controls should be considered for applicability to other

plant personnel whose actions, while on duty, may affect plant safety or the

orderly conduct of facility operation.

Licensees should assure dissemination

of these administrative requirements to affected personnel.* It is also

requested that licensees have their licensed personnel review this Circular

and IE Information Notice 79-20, Revision 1, as well as Regulatory Guide 1.114.

No written response to this Circular is required. If you require additional

information regarding this matter, contact the Director of the appropriate

NRC Regional Office.

"A copy of this Circular was mailed directly to each licensed reactor operator

and senior reactor operator.

Attachment 1

IN 85-53

July 12, 1985 Attachment

IEC 81-02

February 9, 1981

RECENTLY ISSUED

IE CIRCULARS

Circular

Date of

No.

Subject

Issue

Issued to

81-01

Design Problems Involving

Indicating Pushbutton

Switches Manufactured by

Honeywell Incorporated

1/23/81

All power reactor

facilities with

an OL or CP

All radiography

licensees

All teletherapy

licensees

80-25

80-24

80-23

80-22

80-21

Case Histories of

Radiography Events

AECL Teletherapy Unit

Malfunction

Potential Defects in Beloit

Power Systems Emergency

Generators

Confirmation of Employee

Qualifications

Regulation of Refueling

Crews

12/5/80

12/2/80

10/31/80

All power reactor

facilities with

OL or a CP

10/2/80

All holders of a

power reactor OL or CP

architect-engineering

companies and nuclear

steam system suppliers

9/10/80

All holders of a

power reactor OL or CP

80-20

Changes in.

Dimensions

Safe-Slab Tank

8/21/80

80-19

80-18

80-17

Noncompliance with

License Requirements for

Medical Licensees

10 CFR 50.59 Safety

Evaluations for Changes to

Radioactive Waste Treatment

Systems

Fuel Pin Damage Due to Water

Jet from Baffle Plate Corner

8/26/80

8/22/80

7/23/80

All Part 50 and Part

70 fuel facility

licensees

All medical licensees

All power reactor

facilities with an

OL or CP

All holders of PWR

OLs and PWR CPs

OL = Operating Licenses

CP = Construction Permit

Attachment 2

IN 85-53

July 12, 1985

LIST OF RECENTLY ISSUED

IE INFORMATION NOTICES

Information

Date of

Notice No.

Subject

Issue

Issued to

85-52

85-51

85-50

85-49

Errors In Dose Assessment

Computer Codes And Reporting

Requirements Under 10 CFR

Part 21

Inadvertent Loss Or Improper

Actuation Of Safety-Related

Equipment

Complete Loss Of Main And

Auxiliary Feedwater At A PWR

-Designed By Babcock & Wilcox

Relay Calibration Problem

Respirator Users Notice:

Defective Self-Contained

Breathing Apparatus Air

Cylinders

Potential Effect Of Line-

Induced Vibration On Certain

Target Rock Solenoid-Operated

Valves

Clarification Of Several

Aspects Of Removable Radio- active Surface Contamination

Limits For Transport Packages

7/10/85

7/10/85

7/8/85

7/1/85

6/19/85

6/18/85

6/10/85

85-48

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL or CP, research, and test reactor, fuel cycle and

Priority 1 material

licensees

All power reactor

facilities holding

an OL or CP

All power reactor

facilities holding

an OL

All power reactor

facilities holding

an OL or CP

85-47

85-46

85-45 Potential Seismic Interaction 6/6/85 Involving The Movable In-Core

Flux Mapping System Used In

Westinghouse Designed Plants

OL = Operating License

CP = Construction Permit