Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage RacksML031130349 |
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: |
09/08/1987 |
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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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-nr IN-87-043, NUDOCS 8709010085 |
Download: ML031130349 (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>. |
- >
I
Q
SSINS No.: 6835 IN 87-43 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON D.C. 20555 September 8, 1987 NRC INFORMATION NOTICENO. 87-43: GAPS IN NEUTRON-ABSORBING MATERIAL
,INHIGH-DENSITY SPENT FUEL STORAGE
RACKS
Addressees
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This notice is to alert recipients to a potentially significant problem per- taining to gaps identified in the neutron absorber component of the high- density spent fuel storage racks at Quad Cities Unit 1. The safety concern is
that certain gaps might excessively reduce the margin of nuclear subcriticality
in the fuel pool. The NRC expects that recipients will review this notice for
applicability to their facilities and consider actions, if appropriate, to
preclude a similar problem occurring at their facilities. However, suggestions
in-this notice do not constitute NRC requirements; therefore, no specific
action or written response is required..
Description of Circumstances
On May 1, 1987, Commonwealth Edison Company (CECO), the licensee at Quad Cities
1 and 2, presented data to the NRC regarding gaps measured in Boraflex,.a
neutron-absorbing material used in the high-density fuel storage racks manufac- tured by the Joseph Oat Corporation (OAT). Boraflex is a trade name for a
boron carbide dispersion in an elastomeric silicone matrix manufactured by
Bisco Products, Inc. (BISCO). Data pertaining to the gap size and distribution
had been obtained by National Nuclear Corporation.(NNC) under.contract to CECO.
The licensee had retained Northeast Technology Corporation (NETCO) to interpret
the data. NETCO prefaced their assessment as preliminary, noting that avail- able data was limited, but concluded that the gap formation mechanism may be
related to large local stresses in the Boraflex from fabrication-induced re- straint within the rack and to tearing and shrinkage of the material..
The average gap size is 1-1/2 inches, with the largest 4 inches.. The gaps
occur in the.upper two-thirds of the cell length. -
709010085
IN 87-43 September 8, 1987 These gaps are inferred from anomalies in "blackness" testing results by NNC.
The existence of a gap in the Quad Cities neutron absorber panel has been
confirmed by underwater neutron radiography conducted by Nusurtec, Inc.
CECO also discussed the effects these gaps might have on the approved safety
analysis for the spent fuel storage racks. CECO used conservative assumptions
for gap size, gap location, and fuel burnup. Considerable margin in k-eff
appears to be available before the licensing limit of 0.95 would be approached.
In July 1986, Wisconsin Electric Company, the licensee at Point Beach 1 and 2, reported to the NRC that test coupons of Boraflex material had shown consider- able degradation under high radiation. However, the licensee asserted that
this result did not represent the actual condition of Boraflex used in its
spent fuel storage racks because of differences in methods of encapsulation, sample geometry, and handling frequency. Additionally, the coupons had been
subjected to about 5 times more radiation than is associated with the average
fuel rack position. Subsequent examination of full-length panels disclosed
two results: in one panel examined for effects of the water environment but
exposed to negligible gamma radiation, there was no degradation of the Boraflex.
In another panel exposed to significant gamma radiation, 1-2 percent of the
surface showed a gray discoloration at the edges, similar to the degradation
of the coupons.
Discussion:
The concern is that separation of the neutron-absorbing material used in high
density fuel storage racks might compromise safety. Although Quad Cities
reports that its racks, even with gaps in the Boraflex as large as 4 inches, can meet the criticality criterion of k-eff less than or equal to 0.95, this
may not be the case for larger gaps or for other plants. A list of the 31 sites
using Boraflex is given in Attachment 1. Related information is given in
"Behavior of High-Density Spent-Fuel Storage Racks," EPRI NP-4724, Electric
Power Research Institute, August 1986.
Efforts to understand the gap formation have revealed several topics on which
information is needed. Accordingly, the material supplier (BISCO) and the
Electric Power Research Institute (EPRI) have undertaken research programs
to collect this information. Some of their objectives are described below.
The BISCO program aims to establish with increased accuracy the relationship
between radiation dose and size changes. The program also evaluates the
potential effects of handling and restraint, during and subsequent to the fuel
rack fabrication, on gap formation.
The EPRI program will correlate data from utilities' neutron absorber coupon
surveillance programs. EPRI will further examine data obtained from CECO, as
well as from BISCO and other sources, to improve the understanding of possible
or actual gap formation models, including the effects of rack fabrication
methods and irradiation damage mechanisms. The EPRI Program will also attempt
IN 87-43 September 8, 1987 to model the specific Quad Cities experience considering absorbed gamma dose as a
function of axial elevation, neutron absorbing sheet restraint, and fractional
change in length.
The effect of rack design and manufacturing methods on the consequences of
stress, temperature, and chemical environment to irradiated Boraflex is uncer- tain. Recent blackness test results at Turkey Point, who uses a Westinghouse
spent fuel storage rack, did not indicate the presence of gaps in the Boraflex.
The research programs are designed to evaluate each consequence and, In partic- ular, to improve the understanding of stress caused by method of attachment of
the Boraflex panel to the stainless steel wall of the cell. -
Together, these programs are designed to improve the industry understanding of
the safety implications of the observed gaps in the Boraflex neutron absorber
component of the OAT high-density spent-fuel storage racks at Quad Cities.
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.
hares E. Rossi, Director
_ _ - - Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge
(301) 492-8196 Albert D. Morrongiello
(309) 654-2227 Attachments:
Attachment 1
1. List of Plants Using Boraflex IN 87-43 Structures in the Spent Fuel Pool September 8, 1987
2. List of Recently Issued NRC Information Notices LIST OF PLANTS WITH BORAFLEX
STRUCTURES IN THE SPENT FUEL POOL
1. Arkansas 1,2 16. Peach Bottom 2.3
2. Beaver Valley 1 17. Pilgrim
3. Diablo Canyon 1,2 18. Pt. Beach 1,2
4. Calvert Cliffs 2 19. Pr. Island 1,2
5. Farley 1,2 20. Quad Cities 1,2*
6. Fermi 2* 21. Rancho Seco*
7. Ft. Calhoun 22. River Bend
8. Ginna 23. Robinson 2
9. Grand Gulf 1,2* 24. Summer*
10. McGuire 1,2 25. Trojan
11. Millstone 1,2,3 26. Turkey Pt. 3,4
12. Nine Ni. Pt. 1,2 27. Waterford 3
13. North Anna 1,2 28. Seabrook 1,2
14. Oconee 1,2,3 29. Watts Bar 1,2
15. Oyster Creek* 30. Comanche Peak 1,2
31. Harris
- Plants having spent fuel storage racks fabricated by Joseph Oat Corporation.
/ \_J Attachment 2 IN 87-43 September 8, 1987 LIST OF RECENTLY ISSUED
INFORMATION NOTICES 1987 Tnfnrwmtinn n.._ --
uasu or
Noti c No. Subfect Issuance Issued to
87-42 Diesel Generator Fuse 9/4/87 All nuclear power
Contacts reactor facilities
holding an OL or CP.
87-41 Failures of Certain Brown 8/31/87 All nuclear power
Boveri Electric Circuit reactor facilities
Breakers holding an OL or CP.
87-40 Backseating Valves Routinely 8/31/87 All nuclear power
to Prevent Packing Leakage reactor facilities
holding an OL or CP.
87-39 Control of Hot Particle 8/21/87 All nuclear power
Contamination at Nuclear reactor facilities
Power Plants and spent.fuel
storage facilities
holding an NRC
license or CP.
87-38 Inadequate or Inadvertent 8/17/87 All nuclear power
Blocking of Valve Movement reactor facilities
holding an OL or CP.
87-37 Compliance with the General 8/10/87 All persons specifi- License Provisions of cally licensed to
10 CFR Part 31 manufacture or to
Initially transfer
devices containing
radioactive material
to general licensees, as defined in 10 CFR
Part 31.
87-36 Significant Unexpected 8/4/87 All nuclear power
Erosion of Feedwater Lines reactor facilities
holding an OL or CP.
87-35 Reactor Trip Breaker. 7/30/87 All nuclear power
u1etinghouse Modal OSm4I6_ - -mactui fEacz11 ties -
Failed to Open on Manual holdthg an OL or
Initiation from the Control CPeploying WDS-416 Room reactor trip Breakers.
OL a Operating License
UNITED STATES CPa Construction Permit
FIRST CLSS MAIL
NUCLEAR REGULATORY COMMISSION POSTAGE
WASHINGTON, D.C. 20555 USNIIC
PERMIT No. 0-67 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
IN 87-43 September 8, 1987 to model the specific Quad Cities experience considering absorbed gamma dose as a
function of axial elevation, neutron absorbing sheet restraint, and fractional
change in length.
The effect of rack design and manufacturing methods on the consequences of
stress, temperature, and chemical environment to irradiated Boraflex is uncer- tain. Recent blackness test results at Turkey Point, who uses a Westinghouse
spent fuel storage rack, did not indicate the presence of gaps in the Boraflex.
The research programs are designed to evaluate each consequence and, in partic- ular, to improve the understanding of stress caused by method of attachment of
the Boraflex panel to the stainless steel wall of the cell.
Together, these programs are designed to improve the industry understanding of
the safety implications of the observed gaps in the Boraflex neutron absorber
component of the OAT high-density spent-fuel storage racks at Quad Cities.
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 Contacts: Vern Hodge
(301) 492-8196 Albert D. Morrongiello
(309) 654-2227 Attachments:
1. List of Plants Using Boraflex
Structures in the Spent Fuel Pool
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
0// /87
- OGCB:DOEA:NRR *AC/ECEB:DEST:NRR *RI:QUAD *PPMB:ARM *t/dGCB:DOEA:NRR
CVHodge CMcCracken AMorrongiello TechEd CHBerlinger
08/20/87 08/26/87 08/25/87 07/17/87 08/24/87
IN 87-XX
t 'August
xx, 1987 to model the specific Quad Cities experience utilizing absorbed gamma dose as a
function of axial elevation, fractional change in length and neutron absorbing
sheet restraint.
The effect of rack design and manufacturing methods on the consequences of
stress, temperature, and chemical environment to irradiated Boraflex is uncer- tain. Recent blackness test results at Turkey Point, who uses a Westinghouse
spent fuel storage rack, did not Indicate the presence of gaps in the Boraflex.
The research programs are designed to evaluate each consequence and, in partic- ular, to improve the understanding of stress caused by method of attachment or
entrapment of the Boraflex panel to the stainless steel wall of the cell.
Together, these programs are designed to improve the industry understanding of
the safety implications of the observed gaps in the Boraflex neutron absorber
component of the OAT high-density spent-fuel storage racks at Quad Cities. To
date, the NRC has not received information to prompt a more immediate address- ing of this issue.
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 Contacts: Vern Hodge
(301) 492-8196 Albert D. Morrongiello
(309) 654-2227 Attachments:
1. List of Plants Using Boraflex
Structures in the Spent Fuel Pool
2. List of Recently Issued Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR
_r~d~t-_(_CERossi
6 b0 On08//87 OGCB:DOEA:NRR AC/ CEB:DEST:NRR Rr:QUAD *PPMB:ARM C/OGCB:DOEA:NRR4 CVHodge CMcCracken AMorrongiello TechEd CHBerlinger CP6
084;0/87 o8/aIb/87 08/;S787 07/17/87 08Lpt/87
IN 87-XX
July xx, 1987 of maximum gap size, on which the determination of k-eff rests. MaJor uncer- tainties in this picture include isotropy of volume changes, damage mechanism, and influence of stress, temperature, and chemical environment.
Volume changes are assumed isotropic. If untrue, the presently estimated
maximum gap size would be significantly affected.
The radiation damage mechanism is uncertain. Crosslinking leads to shrinkage, whereas scissioning leads to increased friability of the material. In the
absence of low dose data, it is presently assumed that crosslinking damage is
proportional to dose; thus it is thought that crosslinking is about complete at
1-2 E 10 rads. The degraded Point Beach coupons were given a dose of this
magnitude, however the essentially nondegraded Point Beach panels and Quad
Cities panels and representative positions in spent fuel pool storage racks are
associated with doses from 3 to 6 times smaller than this range of values.
Stress, temperature, and chemical environment may influence the estimate of
maximum gap size and hence pool criticality. In particular, to improve the
understanding of stress, the EPRI program will determine the dependence of gap
formation on the method of attaching the Boraflex panel to the stainless steel
wall of the storage rack cell.
Together, these programs are designed to improve the industry's understanding
of the safety implications of the observed degradation of Boraflex.
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 Contacts: Vern Hodge
(301) 492-8196 Albert D. Morrongiello
(309) 654-2227 Attachments:
1. List of Potentially Affected Plants
2. List of Recently Issued Information Notices
OGCB:DOEA:NRR RI:QUAD PPMB:ARM C/OGCB:DOEA:NRR D/DOEA:NRR
CYHodge AMorrongiello TechEd CHBerlinger CERossi
07/ /87 07/ /87 07/11/87 07/ /87 07/ /87
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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)
- 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)
- 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)
- 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)
- 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)
- 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)
- 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)
- 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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