Posttensioned Containment Tendon Anchor Head FailureML031180645 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, 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, 05000262, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Issue date: |
02/06/1985 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-85-010, NUDOCS 8502060136 |
Download: ML031180645 (4) |
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Similar Documents at Beaver Valley, Millstone, Hatch, 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, 05000262, 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 [[: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 [[:05000262]] 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 [[: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 [[:05000262]] 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 85-10
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 February 6, 1985 IE INFORMATION NOTICE NO. 85-10: POSTTENSIONED CONTAINMENT TENDON ANCHOR
HEAD FAILURE
Addressees
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose
This information notice is provided to alert recipients of current information
relating to a potentially significant problem regarding recent failures of
170-wire posttensioned containment tendon anchor heads at Unit 2 of the Farley
Nuclear Station. It is expected that recipients will review the information
for applicability to their facilities and consider actions, if appropriate, to
detect a similar problem at their facilities. However, suggestions contained
in this information notice do not constitute NRC requirements; therefore, no
specific action or written response is required.
NRC is continuing to obtain and evaluate pertinent information. If specific
actions are determined to be required, an additional notification will be made.
Description of Circumstances
Farley Unit 2 On January 28, 1985, while conducting a preintegrated leak rate test walkdown
of the exterior of the containment structure at the Farley Unit 2 facility, an alert utility worker noted grease leakage and a deformed vertical tendon
anchor grease cap on the top of the containment ring beam. When the grease
cap on the same tendon was inspected in the tendon access gallery, it also
revealed a deformed grease cap. Removal of the grease cap showed that the
field anchor head had broken into seven pieces. The posttensioning force
(approximately 1.5 x 10° pounds) also had been released and numerous broken
wires from the 170-wire tendon were found.
On the basis of this finding, the utility removed some additional tendon anchor
grease caps. Of the first eight anchor heads uncovered for inspection, one was
found to be cracked. Inspection was curtailed until the cracked anchor head
can be detensioned. The tendon associated with this anchor head is still
transmitting posttensioning force to the containment. The utility determined
from their records that the broken anchor head and the cracked anchor head have
the same fabrication lot control number.
8502060136
SSINS No.: 6835 IN 85-10 Additionally, the utility has sent some of the pieces of the broken anchor head
to two laboratories for a series of tests for failure analysis, including tests
on metallurgical, mechanical, chemical and other physical properties. Testing
of the corrosion inhibitor grease is under way.
Currently, the utility has personnel from the architect-engineer and the
material supplier on-site in the continuing investigation. Neither the NRC
nor the licensee has yet fully integrated the information regarding the results
of previous tendon surveillance activities at the Farley site into this infor- mation notice. Oral information from the licensee indicates the tendons at K
Farley Unit 2 were posttensioned in early 1977. The unit has been operational
since May 1981. The specific tendon whose anchor head failed and the one found
with a cracked anchor head were not included in the sample of tendons that were
subjected to surveillance activities since the plant began operation. Thus, there is no definitive information currently available on the time of occurrence
of the breakup of the one anchor head or the crack formation in the other
anchor head.
While no specific conclusions have been reached at this time regarding the
cause of the failures, the NRC believes that based on the conversations with
the supplier, INRYCO, that all material from the same fabrication lot control
number as the failed heads was utilized exclusively at Farley Unit 2.
The previous history of anchor head failures before the event at Farley Unit 2, in nuclear applications, has been confined to occurrences during the construction
phase (during or shortly after posttensioning). It is-during-this time-that
the tendon system, including the anchor head, undergoes the maximum loading
force.
As background information, previous 170-wire tendon anchor head failures during
construction at other facilities are briefly summarized below.
Bellefonte Units 1 and 2
During 1975 and 1976 a series of eight rock anchor heads, supplied by INRYCO
for the containments at Bellefonte Units 1 and 2, failed during construction
installation. In the phased construction process these 170-wire assemblies
were sealed for long periods in a highly alkaline water environment. These
anchor heads were to be coupled to the posttensioned containment vertical
tendons to serve as a direct tie between the containment and the rock foundation
material. In these instances the anchor head also broke into several pieces.
The licensee's investigations completed on these failures cited several possible
contributors. These included: (1) high anchor head stress as a result of a
1.4-inch-diameter hole in the head for grout passage, (2) inclusions in the
steel found oriented parallel to the final failure plane, (3) bending of shims J
and anchor plate, and (4) unknown environmental conditions which facilitated
stress corrosion cracking. The NRC had an independent study made that concluded
possible stress corrosion cracking as the initiator.
The resolution of the problem resulted in the removal of all the anchor heads
and replacement with new anchor heads made from a vacuum degassed (cleaner)
SSINS No.: 6835 IN 85-10 steel with the center grout hole eliminated and the anchor head coated for
temporary environmental protection. The NRC is aware of no further failures
at Bellefonte after this corrective action.
Byron Units 1 and 2 In November of 1979 two 170-wire anchor heads on horizontal tendons were reported
to have failed during construction of the Byron containments. One failure
occurred one day after stressing and seating the tendon and the other occurred
13 days after stressing and seating. By the end of January 1980, two additional
anchor heads had been reported as having failed. The supplier of the anchor
heads was INRYCO. Investigations were made by INRYCO on the material from seven
separate fabrication lots. It was found that the basic steel material used in
several of the batches had been manufactured by a process that utilized vanadium
grain refinement causing an incompatibility with the postfabrication heat
treatment. This resulted in a different steel chemistry that would have
required a higher temperature for proper heat treatment. As a result of this
conclusion all anchor heads that had received improper heat treatment for the
basic steel chemistry were removed and replaced. The NRC is not aware of any
failures at Byron since the corrective action.
Discussion
Because the integrity of the posttensioned concrete containment structure is
based on a highly redundant system of numerous tendon elements (several hundred),
the failure of one such element in a family of tendons does not jeopardize
containment structural capability. It does, however, necessitate a determination
that a mechanism or systematic problem has not arisen under service conditions
when one such failure in a tendon is revealed. Specific tendon geometry, tendon size, containment design details, and location of individual tendons
with lost or lowered strength properties would dictate the critical number of
tendons that could be lost before containment integrity is jeopardized.
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.
rh-Eda-rd L. Jordan Director
L Division of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
R. Shewmaker, IE
(301)492-7432 Attachment: List of Recently Issued IE Information Notices
Attachment
IN 85-10
February 06, 1985 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
85-09 Isolation Transfer Switches 1/31/85 All power reactor
And Post-Fire Shutdown facilities holding
Capability an OL or CP
85-08 Industry Experience On 1/30/85 All power reactor i
Certain Materials Used In facilities holding
Safety-Related Equipment an OL or CP
85-07 Contaminated Radiography 1/29/85 All NRC licensees
Source Shipments authorized to
possess industrial
radiography sources
85-06 Contamination of Breathing 1/23/85 All power reactor
Air Systems facilities holding
an OL or CP-
85-05 Pipe Whip Restraints 1/23/85 All power reactor
facilities holding
an OL or CP
85-04 Inadequate Management Of 1/17/85 All power reactor
Security Response Drills facilities holding
an OL or CP, & fuel
fabrication & pro- cessing -facilities
85-03 Separation Of Primary Reactor 1/15/85 All pressurized water
Coolant Pump Shaft And power reactor
Impeller facilities holding an
OL or CP
85-02 Improper Installation And 1/15/85 All power reactor
Testing Of Differential facilities holding
Pressure Transmitters an OL or CP
85-01 Continuous Supervision Of 1/10/85 All material licensees
Irradiators possessing irradiators
that are not self- shielded and contain
more than 10,000
curies of radioactive
material
OL = Operating License
CP = Construction Permit
|
---|
|
list | - Information Notice 1985-01, Continuous Supervision of Irradiators (10 January 1985)
- Information Notice 1985-02, Improper Installation and Testing of Differential Pressure Transmitters (11 January 1985)
- Information Notice 1985-03, Separation of Primary Reactor Coolant Pump Shaft and Impeller (15 January 1985)
- Information Notice 1985-04, Inadequate Management of Security Response Drills (17 January 1985)
- Information Notice 1985-05, Pipe Whip Restraints (23 January 1985)
- Information Notice 1985-06, Contamination of Breathing Air Systems (23 January 1985)
- Information Notice 1985-07, Contaminated Radiography Source Shipments (29 January 1985)
- Information Notice 1985-08, Industry Experience on Certain Materials Used in Safety-Related Equipment (30 January 1985)
- Information Notice 1985-09, Isolation Transfer Switches and Post-Fire Shutdown Capability (31 January 1985, Topic: Safe Shutdown)
- Information Notice 1985-10, Posttensioned Containment Tendon Anchor Head Failure (6 February 1985)
- Information Notice 1985-11, Licensee Programs for Inspection of Electrical Raceway and Cable Installations (11 February 1985)
- Information Notice 1985-12, Recent Fuel Handling Events (11 February 1985)
- Information Notice 1985-13, Consequences of Using Soluble Dams (21 February 1985, Topic: Hydrostatic)
- Information Notice 1985-14, Failure of a Heavy Control Rod (B4C) Drive Assembly to Insert on a Trip Signal (22 February 1985)
- Information Notice 1985-15, Nonconforming Structural Steel for Safety-Related Use (22 February 1985)
- Information Notice 1985-16, Time/Current Trip Curve Discrepancy of ITE/Siemens-Allis Molded Case Circuit Breaker (27 February 1985)
- Information Notice 1985-17, Possible Sticking of Asco Solenoid Valves (1 March 1985)
- Information Notice 1985-18, Failures of Undervoltage Output Circuit Boards in the Westinghouse-Designed Sold State Protection System (7 March 1985)
- Information Notice 1985-19, Alleged Falsification of Certifications and Alteration of Markings on Piping, Valves, and Fittings (11 March 1985)
- Information Notice 1985-20, Motor-Operated Valve Failures Due to Hampering Effect (12 March 1985)
- Information Notice 1985-21, Main Steam Isolation Valve Closure Logic (18 March 1985)
- Information Notice 1985-22, Failure of Limitorque Motor-Operated Valves Resulting from Incorrect Installation of Pinion Gear (21 March 1985)
- Information Notice 1985-23, Inadequate Surveillance and Postmaintenance and Postmodification System Testing (22 March 1985)
- Information Notice 1985-24, Failures of Protective Coatings in Pipes and Heat Exchangers (26 March 1985, Topic: Ultimate heat sink, Coatings)
- Information Notice 1985-25, Consideration of Thermal Conditions in the Design and Installation of Supports for Diesel Generator Exhaust Silencers (2 April 1985, Topic: Coatings)
- Information Notice 1985-26, Vacuum Relief System for Boiling Water Reactor Mark I and Mark II Containments (2 April 1985, Topic: Coatings)
- Information Notice 1985-27, Notifications to the NRC Operations Center and Reporting Events in Licensee Event Reports (3 April 1985, Topic: Coatings)
- Information Notice 1985-28, Partial Loss of AC Power and Diesel Generator Degradation (9 April 1985, Topic: Coatings)
- Information Notice 1985-30, Microbiologically Induced Corrosion of Containment Service Water System (19 April 1985, Topic: Hydrostatic, Coatings, Biofouling)
- Information Notice 1985-31, Buildup of Enriched Uranium in Ventilation Ducts and Associated Effluent Treatment Systems (19 April 1985, Topic: Coatings)
- Information Notice 1985-32, Recent Engine Failures of Emergency Diesel Generators (22 April 1985, Topic: Coatings)
- Information Notice 1985-33, Undersized Nozzle-To-Shell Welded Joints in Tanks and Heat Exchangers Constructed Under the Rules of the ASME Boiler and Pressure Vessel Code (22 April 1985)
- Information Notice 1985-34, Heat Tracing Contributes to Corrosion Failure of Stainless Steel Piping (30 April 1985, Topic: Hydrostatic)
- Information Notice 1985-35, Failure of Air Check Valves to Seat (30 April 1985)
- Information Notice 1985-35, Failure of Air Check Valves To Seat (30 April 1985)
- Information Notice 1985-37, Chemical Cleaning of Steam Generators at Millstone 2 (14 May 1985)
- Information Notice 1985-38, Loose Parts Obstruct Control Rod Drive Mechanism (21 May 1985)
- Information Notice 1985-39, Auditability of Electrical Equipment Qualification Records at Licensees' Facilities (22 May 1985)
- Information Notice 1985-40, Deficiencies in Equipment Qualification Testing and Certification Process (22 May 1985)
- Information Notice 1985-43, Radiography Events at Power Reactors (30 May 1985, Topic: High Radiation Area, Scaffolding)
- Information Notice 1985-44, Emergency Communication System Monthly Test (30 May 1985, Topic: Health Physics Network)
- Information Notice 1985-46, Clarification of Several Aspects of Removable Radioactive Surface Contamination Limits for Transport Packages (10 June 1985)
- Information Notice 1985-47, Potential Effect of Line-Induced Vibration on Certain Target Rock Solenoid-Operated Valves (18 June 1985)
- Information Notice 1985-48, Respirator Users Notice: Defective Self Contained Breathing Apparatus Air Cylinders (19 June 1985, Topic: Hydrostatic)
- Information Notice 1985-49, Relay Calibration Problem (1 July 1985)
- Information Notice 1985-50, Complete Loss of Main and Auxiliary Feedwater at a PWR Designed by Babcock & Wilcox (8 July 1985)
- Information Notice 1985-51, Inadvertent Loss or Improper Actuation of Safety-Related Equipment (10 July 1985)
- Information Notice 1985-52, Errors in Dose Assessment Computer Codes and Reporting Requirements Under 10 CFR Part 21 (10 July 1985)
- Information Notice 1985-53, Performance of NRC-Licensed Individuals While on Duty (12 July 1985)
- Information Notice 1985-54, Teletherapy Unit Malfunction (15 July 1985)
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