Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System ValvesML031220600 |
Person / Time |
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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: |
03/11/1986 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-86-016, NUDOCS 8603050397 |
Download: ML031220600 (4) |
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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 |
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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 [[: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>. |
- -ma SSINS No.: 6835 un I'sIN 86-16 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, DC 20555 March 11, 1986 IE INFORMATION NOTICE NO. 86-16: FAILURES TO IDENTIFY CONTAINMENT LEAKAGE
DUE TO INADEQUATE LOCAL TESTING OF BWR
VACUUM RELIEF SYSTEM VALVES
Addressees
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose
This notice is to alert recipients to a potentially significant problem involving
the failure to conduct adequate local leak rate tests of containment isolation
valves. It is expected that recipients will review this information for appli- cability to their facilities and consider actions, if appropriate, to preclude
a similar problem occurring at their facilities. However, suggestions contained
in this notice do not constitute NRC requirements; therefore, no specific action
or written response is required.
Past Related Correspondence:
IE Circular 77-11, "Leakage of Containment Isolation Valves with Resilient Seals"
September 6, 1977. Information Notice 79-26, "Break of Containment Integrity",
November 5, 1977. Information Notice 85-71, "Containment Integrated Leak Rate
Tests", August 22, 1985.
Description of Circumstances
During containment integrated leak rate testing, three plants had excessive
leakage associated with the torus-to-reactor-building vacuum breaker valves.
In all of these cases, the leakage was not detected by the local leak rate test
procedure because the valves were not tested with pressure applied in the
direction assumed for an accident.
Browns Ferry 2
Browns Ferry Unit 2 conducted a containment integrated leak rate test in
February 1983 that failed because of an excessive leak rate of about twice the
allowable limit of 1.5 percent per day (0.75La). The leakage path was found to
be through a flange seal on a valve in the torus-to-reactor-building vacuum
breaker system. This valve (designated FCV 64-20) is a butterfly valve bolted
8603050397
IN 86-16 March 11, 1986 into an 18-inch line connecting directly to the torus. The leakage through the
flange seal was reduced to an acceptable rate by tightening flange bolts.
Local leak rate testing, which is required to be performed every 2 years, is
done by applying pressure between FCV 64-20 and a flapper-type check valve that
is located on the reactor building side of the butterfly valve. However, the
leaking flange was on the torus side of FCV 64-20. Consequently, the valve
flange was not included in the local testing, but was tested only during the
integrated testing which is done every 3 to 4 years.
Peach Bottom 2
Peach Bottom Unit 2 conducted a containment integrated leak rate test in June
1985 that produced an excessive leak rate of about three times the allowable
limit of 0.375 percent per day. Most of the leakage was found to be going
through the stem seal of valve AO-2502B, an air-operated butterfly valve located
adjacent to the torus in the vacuum breaker line. An apparently successful
local leak rate test performed on this valve prior to the integrated test had
failed to detect the leakage. Local leak rate testing is done by applying
pressure between valve AO-2502B and the check valve located between the reactor
building and this valve. However, the valve stem for AO-2502B is located on the
torus side of the valve and, as in the Browns Ferry case, this leak path was not
subject to the local leak rate test pressure.
Duane Arnold
During a containment integrated leak rate test at Duane Arnold in July 1985, difficulty was experienced in establishing the test pressure. The problem was
found to be caused by leakage through a hole left by a plug that was missing
from the body of isolation valve CV4305. This valve was part of the
torus-to-reactor-building vacuum breaker system and was located on the torus
side of the vacuum breaker line. The plug had evidently been removed during
maintenance conducted on the valve during the same outage as the integrated
test. An apparently successful local leak rate test, conducted on the valve
after the maintenance, had failed to detect the hole. This failure was due to
the fact that the hole was located on the torus side of the valve disc, and
the test pressure had been applied to the other side of the valve.
Discussion:
NRC regulations (10 CFR 50, Appendix J, Section III.C.1) require that local leak
rate test pressure be applied in the same direction as that which would exist
when the valve would be required to perform its safety function, unless it can
be determined that the results from tests for a pressure applied in a different
direction will provide equivalent or more conservative results. Many facilities
experience problems in applying this rule because of the difficulty of applying
a local test pressure for large isolation valves connected directly to primary
containments. After the Browns Ferry test failure, TVA identified 14 containment
isolation valve flanges on each of the Browns Ferry units that were not being
tested under the local leak rate test procedures then in use. After the Peach
Bottom test, two valves on Unit 2 and five valves on Unit 3 were found to be
oriented so that the valve stems were not being subjected to local leak rate
test pressure.
IN 86-16 March 11, 1986 There are modifications and test techniques that can be applied to cause the
local leak rate test to produce "equivalent or more conservative results." For
example, at Browns Ferry, TVA is committed to solving the valve flange problem
by installing double seals (gaskets) on the problem flanges. Local leak rate
test pressure can be applied between the seals to produce a local test that can
be considered equivalent to or more conservative than internal pressurization.
This technique may also be used on valve stems that are designed to permit
double seals. In some situations valve stem seals may be included in the
normally pressurized boundary by turning the valve around without reducing the
effectiveness of the valve. In some cases special test devices such as a blank
flange may be used to seal the line inboard of the inner isolation valve.
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.
Edwar Hi. Jordan, Director
Divisi'n of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
Don Kirkpatrick, IE
(301) 492-4510
Attachment: List of Recently Issued IE Information Notices
1 - -
Attachment 1 IN 86-16 March 11, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
86-15 Loss Of Offsite Power Caused 3/10/86 All power reactor
By Problems In Fiber Optics facilities holding
Systems an OL or CP
86-14 PWR Auxiliary Feedwater Pump 3/10/86 All power reactor
Turbine Control Problems facilities holding
an OL or CP
86-13 Standby Liquid Control 2/21/86 All BWR facilities
System Squib Valves Failure holding an OL or CP
To Fire
86-12 Target Rock Two-Stage SRV 2/25/86 All power reactor
Setpoint Drift facilities holding
an OL or CP
86-11 Inadequate Service Water 2/25/86 All power reactor
Protection Against Core Melt facilities holding
Frequency an OL or CP
84-69 Operation Of Emergency Diesel 2/24/86 All power reactor
Sup. 1 Generators facilities holding
an OL or CP
86-10 Safety Parameter Display 2/13/86 All power reactor
System Malfunctions facilities holding
an OL or CP
86-09 Failure Of Check And Stop 2/3/86 All power reactor
Check Valves Subjected To facilities holding
Low Flow Conditions an OL or CP
86-08 Licensee Event Report (LER) 2/3/86 All power reactor
Format Modification facilities holding
an OL or CP
86-07 Lack Of Detailed Instruction 2/3/86 All power reactor
And Inadequate Observance Of facilities holding
Precautions During Maintenance an OL or CP
And Testing Of Diesel Generator
Woodward Governors
OL = Operating License
CP = Construction Permit
|
---|
|
list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Fire Barrier)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
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