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) |
|
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 86-14 86-13 86-12 86-11 84-69 Sup. 1 86-10 86-09 86-08 86-07 Loss Of Offsite Power Caused By Problems In Fiber Optics Systems PWR Auxiliary
Feedwater
Pump Turbine Control Problems Standby Liquid Control System Squib Valves Failure To Fire Target Rock Two-Stage
SRV Setpoint Drift Inadequate
Service Water Protection
Against Core Melt Frequency 3/10/86 3/10/86 2/21/86 2/25/86 2/25/86 All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All BWR facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP All power reactor facilities
holding an OL or CP Operation
Of Emergency
Diesel 2/24/86 Generators
Safety Parameter
Display 2/13/86 System Malfunctions
Failure Of Check And Stop 2/3/86 Check Valves Subjected
To Low Flow Conditions
Licensee Event Report (LER) 2/3/86 Format Modification
Lack Of Detailed Instruction
2/3/86 And Inadequate
Observance
Of Precautions
During Maintenance
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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