Limiting Access AuthorizationsML031250123 |
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: |
11/03/1986 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-86-091, NUDOCS 8610290048 |
Download: ML031250123 (8) |
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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.: 6385 IN 86-91 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 November 3, 1986 IE INFORMATION NOTICE NO. 86-91: LIMITING ACCESS AUTHORIZATIONS
Addressees
or
All nuclear power reactor facilities holding an operating license using or
construction permit, and fuel fabrication and processing facilities
possessing formula quantities of special nuclear material.
Purpose
of the weaknesses
This information notice is provided to alert licensees to some and safety. It is
in access control which could have an impact on public health
to
expected that the recipients will review the information for applicability
similar
their facilities and consider actions, if appropriate, to preclude contained in
problems from occurring at their facilities. However, suggestions
no
this information notice do not constitute NRC requirements; therefore, specific action or written response is required at this time.
Description of Circumstances
breaker
Some recent events involving threats to safety, for example unauthorized large
manipulation and misalignment of valves, have occurred at sites where
vital areas
numbers of personnel are granted unescorted access to a number of must be limited
and vital islands. 10 CFR 73.55(d)(7) clearly states that access access
to individuals who require such access to perform their duties. Granting and
to others for expediency or convenience increases the risk of sabotage perpetrators
vandalism by insiders and reduces the likelihood of identifying the
in followup investigations.
with
Two recent examples follow where access was not limited in accordance
10 CFR 73.55:
involving
1. In an Enforcement Conference, a licensee claimed that a condition because
two (2) unlocked and unalarmed vital area doors was not significant access to
all but six (6) of about 4000 people onsite had been authorized
the vital area.
been granted
2. At another site most of the administrative/secretarial staff had had been
access to a vital area because a spare word processing terminal
installed there.
8610290048
IN 86-91 November 3, 1986 As a result of these and other specific instances, an informal survey was
conducted of 18 sites in one NRC region. The data collected showed that 90
percent of the 28,000 active badges allowed access to at least one vital area
and more than 50 percent of the badges allowed access to all vital areas.
A review of the above cases showed that the licensee's programs did not address
specific criteria for establishing "need for access" to vital areas or the
equipment contained therein. In some cases, the plans or procedures simply
indicated that a member of management determines access authorization, but no
standard existed for what constituted need. In other cases management provided
overly broad and nonspecific criteria such as "emergency duties" or "work- related duties."
Discussion:
The above described circumstances are indicative of potential weaknesses in
security programs which could allow individuals access to vital equipment when
no supportable reason for such access exists. The root cause of this weakness
appears to be the lack of adequate criteria to clearly determine the circumstances
which must exist prior to allowing an individual free, unescorted access to
controlled areas of the plant.
While it is recognized that facilities differ, certain basic criteria should
be applied to determine the need for access. As noted in IE Bulletin 79-16 (copy attached), valid need should be based on the performance of specific tasks
on or associated with equipment located in each vital area to which access is
authorized. In addition, vital areas should exclude nonvital equipment and
activities to the extent possible to minimize the number of people requiring
access.
To minimize the number of people granted access, consideration may be given to
(1) removing or limiting unescorted access authorization for those with only
infrequent or administrative needs, and (2) removal of unescorted access
authorization when need no longer exists. In accordance with IE Bulletin 79-16, dated July 26, 1979, access lists should be reviewed every 31 days to eliminate
individuals whose need for access has expired. When only infrequent access is
required, escorted access authorization should be sufficient.
IN 86-91 November 3, 1986 information notice.
No specific action or written response is required by thiscontact the Regional
If you have any questions regarding this matter, please
office or the technical contact
Administrator of the appropriate NRC regional
listed below.
ran,d ir tor
Divisi of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
R. P. Rosano, IE
(301) 492-4006 Attachments:
1. IEB 79-16
2. List of Recently Issued IE Information Notices
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 July 26, 1979 IE Bulletin No. 79-16
VITAL AREA ACCESS CONTROLS
Description of Circumstances
An attempt to damage new fuel assemblies occurred recently at an operating
nuclear reactor facility. During a routine fuel inspection, the licensee
discovered that a chemical liquid had been poured over 62 of 64 new fuel
assemblies. Analysis indicates that the chemical liquid was sodium hydroxide, a chemical stored and used onsite.
The licensee stores new fuel assemblies in dry storage wells on the same
elevation as the spent fuel pool within the Fuel Building, a vital area.
Access to the building is controlled by use of a coded keycard which elec- portals. The licensee issues coded
tronically unlocks the alarmed personnel com- keycards to both licensee and contractor personnel after the successful
addition, licensee site manage- pletion of a background screening program. In keycard
ment-certifies monthly that each individual has the need for a coded building is
in order to perform required duties. Further access within'this
not limited by other barriers or controls.
several
As a result of this incident, an initial licensee audit determined that the
hundred licensee and contractor personnel had access to this area during
period when the attempt to damage the fuel was made. The audit also revealed recording
that one coded keycard reader at a vital area portal was inaccurately were
access data at the alarm station. Also discovered during this audit
indications of frequent "tailgating" on access through the portals. Tailgating
occurs when more than one person passes through a portal on one person's
authorized access. Their passage is therefore not recorded, and unauthorized author- persons could gain entry in this manner. Tailgating does not include
ized access controlled by an escort.
Discussion of Applicable Requirements:
sabotage
10 CFR .73.55(a) requires the licensees to protect against industrial
states that access
committed by an insider in any position. 10 CFR 73.55(d)(7) individuals who
to Vital Areas shall be positively controlled and limited to to perform
are authorized access to vital equipment and who require such access
their duties. Specific commitments implementing this regulation are described
in each licensee's approved Security Plan.
Attachment 1 IN 86-91 lovember 3, 1986 Paqe I of 4
NRR, in their meetings with the licensees in March 1977 to explain £ 73.55 of
what would constitute an acceptable plan, explained that positive control
access to a vital area consisted of two elements: first, that the person
requesting entry has the necessary background screening and need toandperform second, Job related functions to be authorized access to that Vital Area, func- that he has a need at that specific time to enter to perform a specific
tion. This is comparable to gaining access to a classified document; you need
both a clearance and a need to know.
would
In approving security plans, NRR assumes that the determination of need should
be based upon a valid need and not convenience. Furthermore, access reason- be authorized to a minimum number of people, and licensees should use
able alternatives to minimize the number of personnel and frequency of access.
Acceptance Criterion 5.B of the Security Plan Evaluation Report (SPER)
Workbook, dated January 1978, states that the licensee must commit to pro- viding positive access control to Vital Areas by:
1) Limiting access to authorized personnel.
2) Requiring positive identification prior to entry.
3) Requiring an established need for access.
4) Maintaining records of entry, exit and reason for entry.
5) A system for control within the Vital Area.
NRR Review Guideline #21 suggests that blanket access authorizations should
method of indicating the Vital
not be granted by stating that an acceptable to
of each vital
Areas to which access is authorized includes a record encoded to permit access area
which the holder is authorized access, and the card is
to only those Vital Areas to which the individual has -been granted access.
person
Review Guideline 123 states that for access to a Type I Vital Area, the individual
must be authorized entry by the shift supervisor or other designated in the Type I
who has been informed of the estimated length of time to be spent
Vital Area.
and the
There needs to be some balance attained between operational necessity entry is to
administrative burden of validating the need for access each time to all
be afforded. Many licensees grant "permanent access authorization"
of the frequency or dura- persons requiring access to vital areas, regardless and guidelines from NRR
tion of the need. This is contrary to the regulations
cited above.
Attachment 1 IN 86-91 November 3, 1936 July 26, 1979 IE Bulletin No. 79_16 Action to be Taken by Licensee:
1. Establish criteria for granting unescorted access to each vital area, which shall be based upon the following:
a. A screening program meeting ANSI N18.17. -
contained
b. The individual has a valid need for access to the equipment need is based
in each vital area to which access is authorized. Valid
tasks upon
upon assigned duties requiring the performance of specific
vital area to
or associated with specific equipment located in each
which access is granted. Valid need to enter one vital area shall
not necessarily indicate that the person has a need to enter any other
vital area.
days.
2. An access list will be established for each area not to exceed 31 list only for the duration of the
An individual will be on the access
has a valid need for unescorted
task to be performed. If an individual
this
access for a single entry or for intermittent occasions during
prepared. All access
period, a separate daily access list shall be
or his
lists shall be approved by the station manager (or equivalent)
designated representative.
upon
3. Individuals, will be removed from the access list immediately area
termination of need. If an individual has not entered the vital
during the effective period of the access list (not to exceed 31 days)
the need for access should be reassured prior to extending the authoriza- be
tion. To ensure that these actions are taken, the access list shall
reviewed and reapproved at least every 31 days.
the criteria
4. Void access authorizations for all personnel not satisfying and reissue
in lafb and where appropriate, reprogram the key card system
authori- key cards that are coded to implement the above vital area access
zation program.
of access
5. Develop reasonable alternatives so that the number and frequency
to vital areas can be minimized consistent with safe operations.
additional
6. Establish emergency procedures where, during an emergency, throughout
authorized personnel, meeting criteria in la&b, can move freely
Upon securing
the vital areas with their entry and exit being recorded. and normal access
from the emergency, the entry/exit record will be reviewed, control will be reestablished.
7. Prevent tailgating by one or more of the following:
Attachment I
IN 86-91 Aovember 3, 1986 IE Bulletin No. 79-16 July 26, 1979 a. Establish procedures that require authorized personnel to prevent
other-personnel, including those authorized unescorted access, from
tailgating. Ensure all authorized personnel are trained in the proce- proce- dure, and establish a management program that ensures that the
dure is properly performed.
b-. Acquire equipment, such as turnstiles, to prevent tailgating. Ensure
that such equipment will not deny access or egress under emergency
conditions.
c. Station a guard, watchperson or escort at the vital area access portal.
This alternative would be most useful when there is a large number and
frequency of access, such as occurs with containment during refueling.
d. By any other means that achieve this objective.
8. Assign corporate responsibility for management oversight of VA access
control and require personal involvement to ensure that all intermediate in
levels of management are properly discharging their responsibilities
this regard.
Conduct routine functional tests of the electronic access control system,
9. and proper
including each key card reader, to verify (i) its operability
of the data recorded. This test should
performance, and (ii) the accuracy 73.55(g).
be incorporated into the seven-day test required by 10 CFR
an operating
10. Report in writing within 45 days (for facilities with (including
license) the actions you have taken and plan to take a
should be submitted
schedule) with regard to Items 1 through 9. Reports should
to the Director of the appropriate NRC Regional Office and a copy Division of
be forwarded to the NRC Office of Inspection and Enforcement, Safeguards Inspection, Washington, D.C. 20555.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80. generic Approval was
problems.
given under a blanket clearance specifically for identified
Attachmtont 1 IN 86-91 November 3, 1986 Attachment 2 IN 86-91 November 3, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
Requests To Dispose Of Very 11/3/86 All power reactor
86-90 facilities holding
Low-Level Radioactive Waste
Pursuant to 10 CFR 20.302 an OL or CP
Uncontrolled Rod Withdrawal 10/16/86 All BWR facilities
86-89 holding an OL or CP
Because Of A Single Failure
Main Steam Safety Valve Test 10/16/86 All power reactor
86-05 facilities holding
Sup. 1 Failures And Ring Setting
Adjustments an OL or CP
Traceability And Material 10/15/86 All power reactor
86-25 facilities holding
Sup. 1 Control of Material And
Equipment, Particularly an OL or CP
Fasteners
Compensatory Measures For 10/15/86 All power reactor
86-88 facilities holding
Prolonged Periods Of Security
System Failures an OL or CP; fuel
fabrication and
processing facilities
Loss Of Offsite Power Upon An 10/10/86 All power reactor
86-87 facilities holding
Automatic Bus Transfer
an OL or CP
Clarification Of Requirements 10/10/86 All registered users
86-86 of NRC certified
For Fabrication And Export Of
Certain Previously Approved packages
Type B Packages
Enforcement Actions Against 10/3/86 All NRC medical
86-85 licensees
Medical Licensees For
Willfull Failure To Report
Misadministrations
Rupture Of A Nominal 9/30/86 All NRC medical
86-84 institution licensees
40-Millicurie Iodine-125 Brachytherapy Seed Causing
Significant Spread Of
Radioactive Contamination
OL - Operating License
CP = Construction Permit
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list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986, Topic: Feedwater Heater)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986, Topic: GOTHIC)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Fire Barrier, Overspeed trip, Overspeed, Water hammer)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib, Local Leak Rate Testing, Integrated leak rate test)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
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