Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1ML031220538 |
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: |
02/03/1986 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-86-006, NUDOCS 8601290056 |
Download: ML031220538 (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 86-06 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 February 3, 1986 IE INFORMATION NOTICE NO. 86-06: FAILURE OF LIFTING RIG ATTACHMENT,WHILE
LIFTING THE UPPER GUIDE STRUCTURE AT
ST. LUCIE UNIT 1
Addressees
All nuclear power facilities holding an operating license (OL) or a construction
permit (CP). .
Purpose
This notice is provided to advise licensees of a potentially significant problem
that occurred during the movement of a heavy load over the reactor core. It is
expected that recipients will review this information for applicability to their
facilities and consider actions, if appropriate, to preclude similar problems at
their facilities. However, the suggestions contained in this notice do not
constitute NRC requirements; therefore, no specific action or written response
is required.
Description of Circumstances
On November 6, 1985, while lifting the upper guide structure from the St.
Lucie Unit 1 reactor vessel, licensee personnel noticed the lifting rig tilt.
The lift was immediately stopped, with the lifting rig canted upward about 6 inches and the guide structure canted downward about 6 inches at one of the
three attachment points. An attempt was promptly made to lower the'load back
to its installed position, but the load cells indicated binding, so the attempt
was terminated after lowering the load a few inches. The 50-ton load was left
suspended about 8 feet above the reactor core.
The licensee declared an Unusual Event. Core alteration containment integrity
was enhanced by resuming full use of the airlocks. Temporary primary manway
covers were installed on bcth hot and cold legs to enhance the nozzle dams.
Survey transits were set up and procedures implemented to monitor the rig and
load for any shifts in their positions.
The licensee and the nuclear steam system supplier, Combustion Engineering, designed and tested a supplementary lifting rig to support the upper guide
structure from the upper portion of the normal rig, using a cable and J-hook
system. On November 9 with the supplementary rig installed, the load was
jacked to a level orientation and moved to its normal parking position in the
refueling pool.
8601290056
IN 86-06 February 3, 1986 Damage caused during the incident included bending the lifting rig and one of
the two guide pins that align the rig with the reactor vessel.
Discussion:
The upper guide structure is shown in Figure 1. It is supported in the reactor
vessel by it§..upper flange. It is aligned by eight alignment keys, four at the
top and fourat the bottom. The structure fits down inside the core support
barrel, just'above the fuel assemblies (see Figure 2). The fuel assembly
alignment plate is the bottom component of the upper guide structure.
The lifting rig is attached to the upper guide structure by three vertically
oriented bolts. These bolts are attached from above the water line by torque
tools that run down the hollow columns of the rig (see Figure 3). Combustion
Engineering's procedure for attaching the rig calls for checking for thread
engagement and torquing each bolt to 50 ft-lbs. The licensee's procedure
omitted the step concerning the check for thread engagement. Subsequent
inspection of the bolt that had pulled loose indicated that part of the last
thread was stripped. It is assumed that this bolt cross-threaded or bound due
to rig to guide structure misalignment during attachment and reached the 50
ft-lb torque requirement with only part of one thread engaged. During the
lift, the few inches of unengaged bolt shaft were pulled through the lifting
rig until the bolt head rested on the rig's surface at the bottom of the
column, resulting in an imperceptible tilt. The resulting lateral load was
initially s6pported by the guide pins. When the rig and guide structure were
lifted about 8 feet, where the guide bushings on the lifting rig reached the
tapered portion of the guide pins, it is surmised that sufficient lateral
motion was permitted to allow the thread of the improperly engaged bolt to slip
free. This caused the observed motion and tilt.
After the guide structure was supported by the supplemental lifting rig and
leveled, it was moved to its normal parking position in the refueling pool.
The short attachment bolts and torque tools were then replaced with full-length
bolts.- The long bolts are designed with heads that rest on surfaces at the top
of the three hollow columns of the lifting rig. This has the advantage of
making anyflmck of full thread engagement more apparent to the personnel
attaching the rig. The guide structure was subsequently returned to its
installed position using the long attachment bolts.
The licensee has not yet decided whether to permanently modify the attachment
bolts. The licensee plans to review all reactor-related lifts for adequacy of
the procedures to ensure proper lift rig attachment, including provisions for
measuring thread engagement.
The potential consequences of dropping heavy loads into the open reactor vessel
were addressed by Unresolved Safety Issue (USI) A-36, "Control of Heavy Loads
Near Spent Fuel." The concern for a UGS drop is that fuel assemblies might be
sufficiently damaged to release the radioactive gases and iodines held within
the fuel-clad gap. Under the reduced containment integrity requirements for
the refueling mode, damage to several fuel assemblies might cause the radiation
dose limits of 10 CFR 100 to be exceeded.
IN 86-06 February 3, 1986 Plant specific calculations were not made for a UGS drop at St. Lucie because
the NRC determined that further calculations were not required after reviewing
initial calculations previously submitted by other reactor facilities in
response to Phase II of USI A-36. Some indication of the consequences of a
UGS drop at St. Lucie can be gained from calculations performed by Combustion
Engineering for a reactor vessel head drop at Waterford 3. The head drop
calculations assumed the reactor vessel head was sufficiently tilted at impact
to directly strike the UGS with the UGS at rest in its normal installed posi- tion. The calculated response velocity of the Waterford UGS was 28 feet per
second, and the resulting vertical stresses imposed on the fuel were not
sufficient to rupture the cladding.
If the St. Lucie UGS had dropped from an 8 foot elevation, its striking velocity
would have been substantially less than the UGS response velocity calculated
for the Waterford head drop. However, the potential for misalignment of the
recesses in the bottom of the UGS (i.e., the fuel assembly alignment plate)
with the fuel assembly upper end fitting posts was not addressed by the Waterford
scenario. If substantial misalignment occurred, the fuel could be subjected to
additional axial loading. Significant misalignment could not occur without
substantial impact damage to the eight keys and keyways, which would also
result in a reduced striking velocity of the UGS as it reached the fuel. On
this basis, significant radioactive gas release is considered to be unlikely, although it has not been shown to be impossible.
No specific action or written response is required by this notice. If you
have any questions regarding this matter, please contact the Regional
Administrator of the appropriate NRC regional office or this office.
ar Jordan, Director
Divisio of Emergency Preparedness
and gineering Response
Office of Inspection and Enforcement
Technical Contacts: S. M. Long, IE
(301) 492-7159 D. E. Sells, NRR
(301) 492-9735 Attachments:
1. Figure 1, Upper Guide Structure Assembly
2. Figure 2, Reactor Internals Assembly
3 Figure 3, Upper Guide Structure Lifting Rig
4. List of Recently Issued IE Information Notices
Attachment 1 IN 86-06 February 3, 1986 EXPANSION
COMPENSATING
RING
CEA
SHROUD
GRID
ASSEMBLY.
CEA SHROUDS
FUEL ASSEMBLY
ALIGNMENT PLATE
Figure 1: Upper Guide Structure Assembly
(St. Lucie Unit 1 FSAR-figure 4.2-10)
UPPER GUIDE
-STRUCTURE SUPPORT
PLATE
Attachment 2 IN 86-06 February 3, 1986 CEA
SHROUD
IN-CORE
-INSTRUMENTATION
OUTLET GUIDE TUBE
CORE
' SUPPORT
BARREL
FUEL
ALIGNMENT
PINS
CORE
-SUPPORT
ASSEMBLY
Am. 3-7/85 Figure 2: Reactor Internals Assembly
(St. Lucie Unit 1 FSAR figure 4.2-7)
At ta chment3 IN 86-06 February 3, 1986 LIFT POINT FOR CRANE HOOK
CLEVIS ASSEMBLY
WORKING PLATFORM
I NSTRUMENT
STALK OPENING
- COLUMN
GUIDE BUSHING FOR
R.V. GUIDE PIN
a PLACES)
- 00
LIFT BOLT
Fi gure 3: Upper Guide Structure Lifting Rig
(St. Lucie Unit 1 FSAR figure 9.1-8)
Attachment 4 IN 86-06 February 3, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Tnfn,'mnfi n
Notice No. Subject
Date oT
Issue T-Issud tn
Issu---- ud -- t
86-05 Main Steam Safety Valve Test 1/31/86 All PWR facilities
Failures And Ring Setting holding an OL or
Adjustments CP
86-04 Transient Due To Loss Of 1/31/86 All power reactor
Power To Integrated Control facilities holding
System At A Pressurized Water an OL or CP
Reactor Designed By Babcock
& Wilcox
86-03 Potential Deficiencies In 1/14/86 All power reactor
Environmental Qualification facilities holding
Of Limitorque Motor Valve an OL or CP
Operator Wiring
86-02 Failure Of Valve Operator 1/6/86 All power reactor
Motor During Environmental facilities holding
Qualification Testing an OL or CP
86-01 Failure Of Main Feedwater 1/6/86 All power reactor
Check Valve Causes Loss Of facilities holding
Feedwater System Integrity an OL or CP
And Water-Hammer Damage
85-101 Applicability of 10 CFR 21 12/31/85 All power reactor
To Consulting Firms Providing facilities holding
Training an OL or CP
85-100 Rosemount Differential 12/31/85 All power reactor
Pressure Transmitter Zero facilities holding
Point Shift an OL or CP
85-99 Cracking In Boiling-Water- 12/31/85 All BWR facilities
Reactor Mark I And Mark II having a Mark I or
Containments Caused By Failure Mark II containment
Of The Inerting System
85-98 Missing Jumpers From Westing- 12/26/85 All Westinghouse
house Reactor Protection designed PWR
System Cards For The Over- facilities holding
Power Delta Temperature Trip an OL or CP
Function
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)
- 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)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986)
- 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)
- 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)
- 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)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991)
- 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)
- 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)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl)
- 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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