Loss of Emergency Boration Capability Due to Nitrogen Gas IntrusionML031130493 |
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 |
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Issue date: |
11/06/1987 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-87-057, NUDOCS 8711020017 |
Download: ML031130493 (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 |
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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]] </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]] </code>. |
/_Je
SSINS No.: 6835 IN 87-57 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 November 6, 1987 NRC INFORMATION NOTICE NO. 87-57: LOSS OF EMERGENCY BORATION CAPABILITY
DUE TO NITROGEN GAS INTRUSION
Addressees
power
All holders of operating licenses or construction permits for nuclear
reactors.
Purpose
potentially
This information notice is being provided to alert addressees to systems. The
significant problems resulting from air/gas intrusion into fluid
units with
event described is also an example of fault propagation between information
shared systems. It is expected that recipients will review the
for applicability to their facilities and consider actions, as this appropriate, contained in information
to avoid similar problems. However, suggestions or
no specific action
notice do not constitute NRC requirements; therefore, written response is required.
Description of Circumstances
and Mode
On May 28, 1987, with Turkey Point Units 3 and 4 in Mode 6 (refueling) to both
5 (cold shutdown), respectively, a loss of all boric acid flowpaths
4 boric acid pumps resulting
units occurred. Nitrogen gas entered the Unit boric acid
in these pumps being gasbound and inoperable. At Turkey Point, theconsists of
system (which is part of the chemical, volume and control system)
four boric acid transfer pumps (two per unit) and three boric acid storage to take
tanks. Each unit normally has one boric acid transfer pump alignedthe charging
suction from a boric acid storage tank, injecting boric acid into
aligned
pump suction header. The second boric acid transfer pump is normally The
to circulate boric acid solution through the boric acid storage tanks.
system alignments, including inter- boric acid system design allows for various transfer pump
connecting Units 3 and 4. During this event, a Unit 3 boric acid
service. Loss of the boric acid
and a boric acid storage tank were out of the
system resulted in the licensee being unable to borate or emergency borate margin.
reactor coolant system to ensure maintenance of the required shutdown
trans- Nitrogen entered the boric acid system through a failed Unit 4 boric acid provided
for this seal, the seal is
fer pump mechanical seal. To provide cooling accumulator
an accumulator tank partially filled with demineralized water. The acid
is given a 40-psi nitrogen overpressure to preclude leakage of the boric
71102 7t- iiC
w
a
IN 87-57 November 6, 1987 across the seal faces (i.e., in the event of seal failure, the differential
pressure will ensure that demineralized water flows into the boric acid
The design of this accumulator provided a continuous nitrogen supply fromsystem).
a
3000-gallon liquid nitrogen storage tank, through a 40-psi pressure regulator, and isolation valves that were normally open. Apparently, as demineralized
water entered the boric acid system through the failed seal, additional
was automatically supplied to the accumulator to maintain pressure. The nitrogen
falling
water level then allowed the nitrogen cover gas to enter the boric acid system
through the failed seal.
Based on previous operating experience, the licensee initially assumed that
loss of boric acid flow to Unit 4 was due to plugging of the piping caused the
inadequate heat tracing and boric acid crystallization. While troubleshootingby
efforts were being conducted to locate the source of the boric acid blockage, the Unit 3 boric acid system was cross connected to Unit 4 to provide a tempo- rary boric acid flowpath. This allowed nitrogen gas intrusion into the
Unit 3 boric acid system and gas binding of the available Unit 3 boric acid transfer
pump, resulting in the loss of both normal and emergency boration flowpaths
both units on May 28 and June 3, 1987. to
On June 3, 1987, when the licensee observed that the water level in an accumu- lator for a Unit 4 boric acid transfer pump could not be maintained within
sight glass, the cause of the problem was properly diagnosed as gas binding the
the pumps-as-a-result of i-trogen intrusiont.--The-lieenseer-restored a boric of
- -
acid flowpath by isolating the affected pump and venting the boric acid
system.
One of the root causes of this event appears to be the design of the accumula- tor cover gas system. A continuous supply of nitrogen allowed the uncontrolled
intrusion of nitrogen gas into the Unit 4 boric acid system through the failed
boric acid transfer pump mechanical seal. To preclude recurrence of this, licensee intends to (1) lock closed the nitrogen supply valves to the pump the
water accumulators, and (2) add nitrogen only in a batch method, as requiredseal
maintain seal pressure. The inability of the operators to recognize the to
symptoms of gas binding in fluid systems permitted nitrogen gas intrusion
into the Unit 3 boric acid system when Units 3 and 4 boric acid systems
were
interconnected. In response, the licensee is providing additional operator
training, upgraded procedures, and emphasizing management control of system
configurations and compliance with procedures.
Discussion:
The event described above is intended to be illustrative of the potential
system inoperability resulting from air/gas intrusion. Since 1981, more than for
90 licensee event reports (LERs) have been submitted to the NRC pertaining
events involving air/gas intrusion. The most significant events of those to
reported have involved: (1) the loss of reactor coolant makeup capability,
(2) the loss of essential service water flow, (3) the inoperability of emer- gency diesel generators (loss of cooling flow), (4) the loss of shutdown
cooling, and (5) water hammer. System or component failures resulting from
air/gas intrusion can be significant.
IN 87-57 November 6, 1987 A previous event involving gas intrusion at McGuire Unit 1 is discussed in IE
Information Notice 82-19, "Loss of High Head Safety Injection Emergency
Boration and Reactor Coolant Makeup Capability." Additional events are dis- cussed in IE Information Notice 83-77, "Air/Gas Entrainment Events Resulting in
System Failures." Air/gas intrusion concerns associated with the residual heat
removal system of pressurized water reactors are addressed in Generic Letter
87-12, "Loss of Residual Heat Removal (RHR) While the Reactor Coolant System
(RCS) is Partially Filled."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
S. D. Stadler, RII
(404)"331-5599 Attachment: List of Recently Issued NRC Information Notices
Attacetnt
IN 87-57 lovevbr 8. 1987 LIST OF RECENTLY ISSUED
INFORYAT101 ItOTICES1987 Iformitlpfl Date of
Kotice lb Subject Issuance Insuvd to
87-56 Improper Hydraulic Control 4/8?7 All helders of OLs
Unit Installation at VA or CPs for boiling
plants. water reactors (CBIRS).
87-SS Pertaele Nbisture/Density 10/28/87 All NHC1icenses
Gauges: Recent Incidents authorized to
of Portable GaugesBeing posse, portable
Stolen or Lost puge.
87-54 Emergency Response Exercises 10/23/7 All holders of L
or CPSfor nuclear
power reactors.
V7-53 Auxiliary F ter Pump 10/20/87 All holders of OLc
Trips Resulting trom Low or CU2for nucleir
Suction Pressure Powr reactors.
87-52 Insulation Breakdo'n of 10/ 7 All holders of DLS
Silicone Rubber-Insulated or Us for nuclear
Single Conductor Cables pow"r reetors.
During High Potential Testing
07-51 Feilure of Low Pressure 10/13/87 All nuclear power
Safety Injection PumpDue reactor fbcilities
to Sael Problems holding en OL or CP.
87-50 Potential LOCAat Migh- 10/1/87 All nuclear power
and Low-Pressure Interfaces reactor facilities
from Fire Damage holding an OL or CP.
07-49 Deficiencies in Outside 108/7 All nucleer power
Containment Flooding reactor facilities
Protection holding en OL or CP.
81-U Informatios Concerning the 10/9/87 All nuclear power
Use of Anaerobic Adhesive/ reactor facilities
Sealants holding an 0L or tP.
OL
CP
FIRST CLASS MAIL
UNITED STATES POSTAGE I FEES PAID
NUCLEAR REGULATORY COMMISSION UUSNRC
WASHINGTON, D.C. 20555 PERMIT No G-87 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
- . 1t
IN 87-57 November 6, 1987 A previous event involving gas intrusion at McGuire Unit 1 is discussed in IE
Information Notice 82-19, "Loss of High Head Safety Injection Emergency
Boration and Reactor Coolant Makeup Capability." Additional events are dis- cussed in IE Information Notice 83-77, "Air/Gas Entrainment Events Resulting in
System Failures." Air/gas intrusion concerns associated with the residual heat
removal system of pressurized water reactors are addressed in Generic Letter
87-12, "Loss of Residual Heat Removal (RHR) While the Reactor Coolant System
(RCS) is Partially Filled."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
S. D. Stadler, RII
(404) 331-5599 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
CHBerlinger
1/Z 7 10/23/87
- RI I *OGCB:DOEA:NRR &/SPLB:DEST:NRR SADDEST: NRR *PPMB:ARM
SDStadler JERamsey JCraig AThadani TechEd
10/01/87 10/06/87 10/ /87 10/ /87 10/06/87
IN 87-XX
October xx, 1987 References:
A previous event involving gas intrusion at McGuire Unit 1 is discussed in TE
Information Notice 82-19, "Loss of High Head Safety Injection Emergency
Boration and Reactor Coolant Makeup Capability." Additional events are dis- cussed in IE Information Notice 83-77, "Air/Gas Entrainment Events Resulting in
System Failures." Air/gas intrusion concerns associated with the residual heat
removal system of pressurized water reactors are addressed in Generic Letter
87-12, "Loss of Residual Heat Removal (RHR) While the Reactor Coolant System
(RCS) is Partially Filled."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
S. D. Stadler, RII
(404) 331-5599 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR *C/OGCB:DOEA:NRR
CERossi CHBerlinger
10/ /87 10/23/87
- RII *OGCB:DOEA:NRR CJWPLB DEST:NRR SAD/DEST:N^f *PPMB:ARM
SDStadler JERamsey JCraig AThadan FJI TechEd
10/01/87 10/06/87 10/26/87 10/1&87 10/06/87
I
IN 87-XX
October xx, 1987 References:
A previous event involving gas intrusion at McGuire Unit 1 is discussed in TE
Information Notice 82-19, "Loss of High Head Safety Injection Emergency
Boration and Reactor Coolant Makeup Capability." Additional events are dis- cussed in IE Information Notice 83-77, "Air/Gas Entrainment Events Resulting in
System Failures." Air/gas intrusion concerns associated with the residual heat
removal system of pressurized water reactors are addressed in Generic Letter
87-12, "Loss of Residual Heat Removal (RHR) While the Reactor Coolant System
(RCS) is Partially Filled."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
S. D. Stadler, RII '
(404) 331-5599 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- RII *OGCB:DOEA:NRR *PPMB:ARM C/OC: OEA:NRR D/DOEA:NRR
SDStadler JERamsey TechEd CHBerlinger CERossi
10/01/87 10/06/87 10/06/87 10/16/87 10/ /87
IN 87-XX
October xx, 1987 To preclude recurrence of this event, the licensee will (1) lock closed the
nitrogen supply valves to the pump seal water accumulators, and (2) add
nitrogen only in a batch method, as required to maintain seal pressure. The
licensee also is providing additional operator training, upgraded procedures, and emphasizing management control of system configurations and compliance with
procedures.
Discussion:
The event described is Intended to be illustrative. Licensees are cautioned
that the types of system inoperability resulting from air/gas intrusion will
vary. Since 1981, more than 90 licensee event reports (LERs) have been submit- ted to the NRC for events involving air/gas intrusion. The events described
include (1) the loss of reactor coolant makeup capability, (2) the loss of
essential service water flow, (3) the inoperability of emergency diesel genera- tors (loss of cooling flow), (4) the loss of shutdown cooling, and (5) water
hammer. The consequences that can result from such a system or component
failure cannot be overemphasized.
References:
A previous event involving gas intrusion at McGuire Unit 1 is discussed in IE
Information Notice 82-19, "Loss of High Head Safety Injection Emergency
Boration and Reactor Coolant Makeup Capability." Additional events are dis- cussed in IE Information Notice 83-77, "Air/Gas Entrainment Events Resulting in
System Failures." Air/gas intrusion concerns associated with the residual heat
removal system of pressurized water reactors are addressed in Generic Letter
87-12, "Loss of Residual Heat Removal (RHR) While the Reactor Coolant System
(RCS) is Partially Filled."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
S. D. Stadler, RII
(404) 331-5599 Attachment: List of Recently Issued NRC Information Notices
RII OG i g f NRR PPMB: M C/OGCB:DOEA:NRR D/DOEA:NRR
SDStadler JE sey TechEd. C/ CHBerlinger CERossi
10/1 /87 10/1C/87 10/6 / 7 10/ /87 10/ /87 wnte V.S6tacr
oK 0ot110.
Zatl
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list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987, Topic: Water hammer)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987, Topic: Excess Flow Check Valve)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987, Topic: License Renewal)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Boric Acid)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed trip)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987, Topic: Boric Acid)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling, Uranium Hexafluoride)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987, Topic: Commercial Grade)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding, Overexposure)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
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