Performance of NRC-Licensed Individuals While on DutyML031180229 |
Person / Time |
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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, Three Mile Island, 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 |
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Issue date: |
07/12/1985 |
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From: |
Taylor J NRC/OE, NRC/OI |
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To: |
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References |
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IN-85-053, NUDOCS 8507110094 |
Download: ML031180229 (7) |
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Similar Documents at 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, Three Mile Island, 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 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
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 Page of 48008220282 Accession No.:
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 Attachment
IN 85-53 IEC 81-02 July 12, 1985 February 9, 1981 RECENTLY ISSUED
IE CIRCULARS
Circular Date of
No. Subject Issue Issued to
81-01 Design Problems Involving 1/23/81 All power reactor
Indicating Pushbutton facilities with
Switches Manufactured by an OL or CP
Honeywell Incorporated
80-25 Case Histories of 12/5/80 All radiography
Radiography Events licensees
80-24 AECL Teletherapy Unit 12/2/80 All teletherapy
Malfunction licensees
80-23 Potential Defects in Beloit 10/31/80 All power reactor
Power Systems Emergency facilities with
Generators OL or a CP
80-22 Confirmation of Employee 10/2/80 All holders of a
Qualifications power reactor OL or CP
architect-engineering
companies and nuclear
steam system suppliers
80-21 Regulation of Refueling 9/10/80 All holders of a
Crews power reactor OL or CP
80-20 Changes in.Safe-Slab Tank 8/21/80 All Part 50 and Part
Dimensions 70 fuel facility
licensees
80-19 Noncompliance with 8/26/80 All medical licensees
License Requirements for
Medical Licensees
80-18 10 CFR 50.59 Safety 8/22/80 All power reactor
Evaluations for Changes to facilities with an
Radioactive Waste Treatment OL or CP
Systems
80-17 Fuel Pin Damage Due to Water 7/23/80 All holders of PWR
Jet from Baffle Plate Corner 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 Errors In Dose Assessment 7/10/85 All power reactor
Computer Codes And Reporting facilities holding
Requirements Under 10 CFR an OL or CP
Part 21
85-51 Inadvertent Loss Or Improper 7/10/85 All power reactor
Actuation Of Safety-Related facilities holding
Equipment an OL or CP
85-50 Complete Loss Of Main And 7/8/85 All power reactor
Auxiliary Feedwater At A PWR facilities holding
-Designed By Babcock & Wilcox an OL or CP
85-49 Relay Calibration Problem 7/1/85 All power reactor
facilities holding
an OL or CP
85-48 Respirator Users Notice: 6/19/85 All power reactor
Defective Self-Contained facilities holding
Breathing Apparatus Air an OL or CP, research, Cylinders and test reactor, fuel cycle and
Priority 1 material
licensees
85-47 Potential Effect Of Line- 6/18/85 All power reactor
Induced Vibration On Certain facilities holding
Target Rock Solenoid-Operated an OL or CP
Valves
85-46 Clarification Of Several 6/10/85 All power reactor
Aspects Of Removable Radio- facilities holding
active Surface Contamination an OL
Limits For Transport Packages
85-45 Potential Seismic Interaction 6/6/85 All power reactor
Involving The Movable In-Core facilities holding
Flux Mapping System Used In an OL or CP
Westinghouse Designed Plants
OL = Operating License
CP = Construction Permit
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list | - Information Notice 1985-01, Continuous Supervision of Irradiators (10 January 1985)
- Information Notice 1985-02, Improper Installation and Testing of Differential Pressure Transmitters (11 January 1985)
- Information Notice 1985-03, Separation of Primary Reactor Coolant Pump Shaft and Impeller (15 January 1985)
- Information Notice 1985-04, Inadequate Management of Security Response Drills (17 January 1985)
- Information Notice 1985-05, Pipe Whip Restraints (23 January 1985)
- Information Notice 1985-06, Contamination of Breathing Air Systems (23 January 1985)
- Information Notice 1985-07, Contaminated Radiography Source Shipments (29 January 1985)
- Information Notice 1985-08, Industry Experience on Certain Materials Used in Safety-Related Equipment (30 January 1985)
- Information Notice 1985-09, Isolation Transfer Switches and Post-Fire Shutdown Capability (31 January 1985, Topic: Safe Shutdown)
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure (6 February 1985)
- Information Notice 1985-11, Licensee Programs for Inspection of Electrical Raceway and Cable Installations (11 February 1985)
- Information Notice 1985-12, Recent Fuel Handling Events (11 February 1985)
- Information Notice 1985-13, Consequences of Using Soluble Dams (21 February 1985, Topic: Hydrostatic)
- Information Notice 1985-14, Failure of a Heavy Control Rod (B4C) Drive Assembly to Insert on a Trip Signal (22 February 1985)
- Information Notice 1985-15, Nonconforming Structural Steel for Safety-Related Use (22 February 1985)
- Information Notice 1985-16, Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded Case Circuit Breaker (27 February 1985)
- Information Notice 1985-17, Possible Sticking of Asco Solenoid Valves (1 March 1985)
- Information Notice 1985-18, Failures of Undervoltage Output Circuit Boards in the Westinghouse-Designed Sold State Protection System (7 March 1985)
- Information Notice 1985-19, Alleged Falsification of Certifications and Alteration of Markings on Piping, Valves, and Fittings (11 March 1985)
- Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect (12 March 1985)
- Information Notice 1985-21, Main Steam Isolation Valve Closure Logic (18 March 1985)
- Information Notice 1985-22, Failure of Limitorque Motor-Operated Valves Resulting from Incorrect Installation of Pinion Gear (21 March 1985)
- Information Notice 1985-23, Inadequate Surveillance and Postmaintenance and Postmodification System Testing (22 March 1985)
- Information Notice 1985-24, Failures of Protective Coatings in Pipes and Heat Exchangers (26 March 1985, Topic: Ultimate heat sink, Coatings)
- Information Notice 1985-25, Consideration of Thermal Conditions in the Design and Installation of Supports for Diesel Generator Exhaust Silencers (2 April 1985, Topic: Coatings)
- Information Notice 1985-26, Vacuum Relief System for Boiling Water Reactor Mark I and Mark II Containments (2 April 1985, Topic: Coatings)
- Information Notice 1985-27, Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 April 1985, Topic: Coatings)
- Information Notice 1985-28, Partial Loss of AC Power and Diesel Generator Degradation (9 April 1985, Topic: Coatings)
- Information Notice 1985-30, Microbiologically Induced Corrosion of Containment Service Water System (19 April 1985, Topic: Hydrostatic, Coatings, Biofouling)
- Information Notice 1985-31, Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment Systems (19 April 1985, Topic: Coatings)
- Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators (22 April 1985, Topic: Coatings)
- Information Notice 1985-33, Undersized Nozzle-To-Shell Welded Joints in Tanks and Heat Exchangers Constructed Under the Rules of the ASME Boiler and Pressure Vessel Code (22 April 1985)
- Information Notice 1985-34, Heat Tracing Contributes to Corrosion Failure of Stainless Steel Piping (30 April 1985, Topic: Hydrostatic)
- Information Notice 1985-35, Failure of Air Check Valves to Seat (30 April 1985)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985)
- Information Notice 1985-38, Loose Parts Obstruct Control Rod Drive Mechanism (21 May 1985)
- Information Notice 1985-39, Auditability of Electrical Equipment Qualification Records at Licensees' Facilities (22 May 1985)
- Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process (22 May 1985)
- Information Notice 1985-43, Radiography Events at Power Reactors (30 May 1985, Topic: High Radiation Area, Scaffolding)
- Information Notice 1985-44, Emergency Communication System Monthly Test (30 May 1985, Topic: Health Physics Network)
- Information Notice 1985-46, Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages (10 June 1985)
- Information Notice 1985-47, Potential Effect of Line-Induced Vibration on Certain Target Rock Solenoid-Operated Valves (18 June 1985)
- Information Notice 1985-48, Respirator Users Notice: Defective Self Contained Breathing Apparatus Air Cylinders (19 June 1985, Topic: Hydrostatic)
- Information Notice 1985-49, Relay Calibration Problem (1 July 1985)
- Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox (8 July 1985)
- Information Notice 1985-51, Inadvertent Loss or Improper Actuation of Safety-Related Equipment (10 July 1985)
- Information Notice 1985-52, Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR Part 21 (10 July 1985)
- Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty (12 July 1985)
- Information Notice 1985-54, Teletherapy Unit Malfunction (15 July 1985)
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