Significant Unexpected Erosion of Feedwater LinesML031130521 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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: |
08/04/1987 |
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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-87-036, NUDOCS 8707290264 |
Download: ML031130521 (8) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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 |
---|
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 [[: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 [[: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 87-36 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555 August 4, 1987 NRC INFORMATION NOTICE NO. 87-36: SIGNIFICANT UNEXPECTED EROSION OF
FEEDVATER LINES
Addressees
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This information notice is provided to alert recipients to a potentially
generic problem pertaining to significant unexpected erosion which resulted
in pipe wall thinning in the safety-related portions of feedwater lines and
other related problems. It is expected that recipients will review the Infor- mation for applicability to their facilities and consider actions, if appro- priate, to preclude a similar problem. However, suggestions contained in this
notice do not constitute NRC redpuirements; therefore no specific action or
written response is required.
Description of Circumstances
At the Trojan Nuclear Plant it was discovered that at least two areas of the
straight sections of the main feedwater piping system experienced wall thinning
to an extent that the pipe wall thickness would have reached the minimum thick- ness required by the design code (ANSI B31.7, "Nuclear Power Piping") during
the next refueling cycle. These areas are in safety-related portions of ASME
Boiler and Pressure Vessel Code (ASME Code) Class 2 piping inside containment.
The pipe wall had thinned in both horizontal and vertical runs that were at
least seven pipe diameters downstream of elbows or other devices that can cause
flow turbulence. Criteria developed by the Electric Power Research Institute
(EPRI Users Manual NSAC-112, "CHEC [Chexal-Horowitz-Erosion-CorrosionJ,I dated
June 1987) would not have required that the pipe wall in these straight sec- tions be examined.
Although the straight sections of eroded 14-inch pipe were slightly thicker
than the minimum required thickness, it was projected that the pipe wall
thickness would erode below the minimum required thickness before the next
major outage. Consequently, the licensee plans to replace this piping before
restart.
02W64' '*
8707290264 Ul
N-J/
IN 87-36 August 4, 1987 The Trojan plant is conducting a failure analysis on the degraded components to
determine the causes and mechanisms involved in the observed wall thinning
event. The NRC is evaluating the data available to determine any generic
implication of the event.
Related Generic Communications:
IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,
1982 provides additional information pertaining to erosion/corrosion in wet
steam piping. Other erosion/corrosion events pertaining specifically to the
feedwater systems (including emergency and auxiliary feedwater) have occurred
in feedwater pump minimum-flow lines, J-tubes in steam generator feedwater
rings, and emergency feedwater supply to a helium circulator.
IE Information Notice 86-106, "Feedwater Line Break," was issued December 16,
1986. It described the then-known details of the December 9,, 1986 failure of
the suction line to a main feedwater pump at Surry Power Station Unit 2.
Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was
issued on March 10, 1987, discussed the effects of the system interactions that
resulted from the line break.
NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on
Juty-9;-987, requested that iTcensees submit information concernffng-thirlf
programs for monitoring the thickness of pipe walls in high-energy single-phase
and two-phase carbon steel piping systems.
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 NRC regional office or this office.
rle
E.RostDirector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Paul C. Wu, NRR
(301) 492-8987 Attachment: List of Recently Issued NPC Information Notices
IN 87-36 August 4, 1987 The licensee believes that the high flow velocity of 22.6 ft/sec, in combina- tion with other operating factors, may be the cause of the thinning.
This thinning was discovered when the steam piping inspection program at the
Trojan plant was expanded to include single-phase piping. Trojan personnel
inspected essentially all safety-related high energy carbon steel piping
inside containment.
In addition, the licensee discovered approximately 30 additional areas of the
main feedwater piping system where the pipe wall had thinned so the thickness
of the pipe wall was either less than the minimum thickness required by the
design code or would have eroded to the minimum required thickness during the
next operating cycle. Of these areas, 10 were in the safety-related portions
of the system, while the rest were in non-safety-related portions. All of
these thirty additional areas were in regions that the EPRI criteria would have
indicated as 'needing examination.
Discussion:
The feedwater system inside containment consists of four lines. Lines A and B
are mirror images, as are Lines C and D. The parameters of the ASME Code Class
2 portion of the piping system are as listed below.
Design Temperature ^ 4450 F
Operating Temperature 4450F
Design Pressure 1125 psi
Operating Pressure 920 psi
Piping Material A-106 GRB
Diameter 14-in. OD
Wall Thickness Nominal 0.593 in.
Wall Thickness Minimal (ANSI B31.7) 0.510 in.
Oxygen Content 4 ppb
pH 9.0
Flow Velocity 22.6 ft/sec @ 100% power
The thinning of the straight sections occurred in Lines A and D.
A number of 45- and 90-degree elbows and two 60-degree elbows were also replaced.
The thickness of the remaining pipe wall in these areas ranged from 0.43 to
0.46 in. The minimum required thickness is 0.499 in., and nominal wall thick- ness at time of installation was 0.593 ir
In the non-safety-related portions of the feedwater lines, a total of 20 pieces
of 14-in. pipe were replaced. This total included elbows as well as some
straight pieces down stream of the elbows or other discontinuities. The
thinning in these segments is very similar to that in the ASME Code Class 2 portion except that the minimum required thickness was 0.44 in.
Trojan personnel also replaced a segment of 30-in. header pipe after identify- ing a localized portion of header pipe that had eroded to 1.018-in. wall.
thickness (a minimum thickness of 1.63 in. was required).
\' Attachment
IN 87-36 August 4, 1987 LIST OF RECENTLY ISSUED
INFORMATION NOTICES 1987 InTornation Dare or
Notice No. Subject Issuance Issued to
87-35 Reactor Trip Breaker, 7/30/87 All nuclear power
Westinghouse Model DS-416, reactor facilities
Failed to Open on Manual holding an OL or
Initiation from the Cortrol CP employing W DS-J'6 PooP reactor trip 6reakers.
87-34 Single Failures inAuxIliary 7/24/87 All holders of an
Feedwater Systems OL or a CP for
pressurized water
reactor facilities.
87-33 Applicability of 10 CFR 7/24/87 All NRC licensees.
Part 21 to Nonlicensees
87-3? Deficiencies In the Testing 7/10/87 All nuclear power
of Nuclear-Grade kctivated reactor facilities
Charcoal. holding an OL or CP.
87-31 8locking. Bracing, and 7/10/87 All NRC licensees.
Securing of Radioactive
Materials Packages in
Transportation.
87-30 Cracking of Surge Ring 7/2/87 All nuclear power
Brackets in Large General reactor facilities
Electric Company Electric holding an AL or CP.
Motors.
87-29 Recent Safety-Related 6/26/87 All NRClicensees
Incidents at Larqe authorized to possess
Irradiators. and use sealed sources
in large irradiators.
87-28 Air Systems Problems at 6/27/87 All nuclear power
U.S. Light Water Reactors. reactor facilities
holding an OL or CP.
OL u Operating License
CP * Construction Permit
UNITED STATES
NUCLEAR REGULATORY COMMISSION FlRST CLASS MAIL
POSTAGE
WASHINGTON, D.C. 20555 USNRC
WASH. D.C.
PERMIT No. a4j
OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
IN 87-36 August 4, 1987 The Trojan plant is conducting a failure analysis on the degraded components to
determine the causes and mechanisms involved in the observed wall thinning
event. The NRC is evaluating the data available to determine any generic
implication of the event.
Related Generic Communications:
IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,
1982 provides additional information pertaining to erosion/corrosion in wet
steam piping. Other erosion/corrosion events pertaining specifically to the
feedwater systems (including emergency and auxiliary feedwater) have occurred
in feedwater pump minimum-flow lines, J-tubes in steam generator feedwater
rings, and emergency feedwater supply to a helium circulator.
FE Info mation Notice 86-106, "Feedwater Line Break," was issued December 16,
1986. It described the then-known details of the December 9, 1986 failure of
the suction line to a main feedwater pump at Surry Power Station Unit 2.
Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was
issued on March 10, 1987, discussed the effects of the system interactions that
resulted from the line break.
NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on
July 9, 1987, requested that licensees submit information concerning their
programs for monitoring the thickness of pipe walls in high-energy single-phase
and two-phase carbon steel piping systems.
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 NRC regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Paul C. Wu, NRR
(301) 492-8987 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
- C/OGCB:DOEA:NRR *PPMB:ARM
CHBerlinger TechEd
07p4 87 07/28/87 07/28/87
- OGCB.DOEA:NRR *ECE :DEST:NRR *AC/ECEB:DEST:NRR *EAD:DEST:NRR
RJKiessel PCWu CEMcCracken JRichardson
07/16/87 07/16/87 07/16/87 07/16/87
IN 87-XX
July xx, 1987 The Trojan plant is conducting a failure analysis on the degraded components to
determine the causes and mechanisms involved in the observed wall thinning
event. The NRC is evaluating the data available and has formed a task force to
determine any generic implication of the event.
Related Generic Communications:
IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,
1982 provides additional information pertaining to erosion/corrosion in wet
steam piping. Other erosion/corrosion events pertaining specifically to the
feedwater systems (including emergency and auxiliary feedwater) have occurred
in feedwater pump minimum-flow lines, J-tubes in steam generator feedwater
rings, and emergency feedwater supply to a helium circulator.
IE Information Notice 86-106, "Feedwater Line Break," was issued December 16,
1986. It described the then-known details of the December 9, 1986 failure of
the suction line to the main feedwater pump at Surry Power Station Unit 2.
Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was
issued on March 10, 1987, discussed the effects of the system interactions that
resulted from the line break.
NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on
July 9, 1987, requested that licensees submit information concerning their
programs for monitoring the thickness of pipe walls in high-energy single-phase
and two-phase carbon steel piping systems.
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 NRC regional office or this office.
Charles E. Rossi, Director
Division of Operational Event Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Paul C. Wu, NRR
(301) 492-8987 Attachment: List of Recently Issued IE Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEAiNRR *PPMB:ARM
CERossi CHBerling ' if TechEd
07/ /87 07/~t/87 07/28/87
- OGCB:DOEA:NRR *ECEB:DEST:NRR *AC/ECEB:DEST:NRR *EAD:DEST:NRR
RJKiessel PCWu CEMcCracken JRichardson
07/16/87 07/16/87 07/16/87 07/16/87
IN 87-XX
July xx, 1987 The Trojan Power Station is conducting a failure analysis on the degraded
components to determine the causes and mechanisms involved in the observed wall
thinning event. The NRC is evaluating the data available and has formed a task
force to determine any generic implication of the event.
Related Generic Communications:
TE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,
1982 provides additional information pertaining to erosion/corrosion in wet
steam piping. Other erosion/corrosion events pertaining specifically to the
feedwater systems (including emergency and auxiliary feedwater) have occurred
in feedwater pump minimum flow lines, J-tubes in steam generator feedwater
rings, and emergency feedwater supply to a helium circulator.
Information Notice 86-106, "Feedwater Line Break," was issued December 16,
1986. It described the, then known, details of the December 9, 1986, failure
of the suction line to the main feedwater pump at Surry Power Station Unit 2.
Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was
issued on March 10, 1987, discussed the effects of the system interactions
which resulted from the line break.
NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on
July 9, 1987, requested that licensees submit information concerning their
programs for monitoring the thickness of pipe walls in high-energy single-phase
and two-phase carbon steel piping systems.
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 NRC regional office or this office.
Charles E. Rossi, Director
Division of Operational Event Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Paul C. Wu, NRR
(301) 492-8987 Attachment: List of Recently Issued IE Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR PPMB:ARJ4 CERossi CHBerlinger TechEd '
07/ /87 07/ /87 07/1V/87
- OGCB:DOEA:NRR *ECEB:DEST:NRR *AC/ECEB:DEST:NRR *EAD:DEST:NRR
RJKiessel PCWu CEMcCracken JRichardson
07/16/87 07/16/87 07/16/87 07/16/87
. . P
IN 87-XX
July xx, 1987 Related Generic Communications:
IE Information Notice 82-22, "Failure in Turbine Exhaust Lines," dated July 9,
1982 provides additional information pertaining to erosion/corrosion in wet
steam piping. Other erosion/corrosion events pertaining specifically to the
feedwater systems (including emergency and auxiliary feedwater) have occurred
in feedwater pump minimum flow lines, J-tubes in steam generator feedwater
rings, and emergency feedwater supply to a helium circulator.
Information Notice 86-106, "Feedwater Line Break," was issued December 16,
1986. It described the, then known, details of the December 9, 1986, failure
of the suction line to the main feedwater pump at Surry Power Station Unit 2.
Supplement 1 to this information notice, which was issued February 13, 1987, provided additional detail on the failure mechanism. Supplement 2, which was
issued on March 10, 1987, discussed the effects of the system interactions
which resulted from the line break.
NRC Bulletin 87-01, "Thinning of Pipe Wall in Nuclear Power Plants," issued on
July 9, 1987, requested that licensees submit information concerning their
programs for monitoring the thickness of pipe walls in high-energy single-phase
and two-phase carbon steel piping systems.
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 NRC regional office or this office.
Charles E. Rossi, Director
Division of Operational Event Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Paul C. Wu, NRR
(301) 492-8987 Attachment: List of Recently Issued IE Information Notices
D/DOEA:NRR C/OGCB:DOEA:NRR PPMB:A
CERossi CHBerlinger TechEd bsf/
07/ /87 07/ /87 07/0(/8 OGCB:DOEA:NRR ECEB: :NRR AC/ECEB:DEST}NR EAD:DESTJIR
RJKiessel PCWu FA<4 CEMcCracke ¢("L__ JRichard on
07/1)/87 07//,/87 071/4 /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, 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)
... further results |
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