Check Valve Inservice Testing Program DeficienciesML031150152 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
08/29/1988 |
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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-88-070, NUDOCS 8808230112 |
Download: ML031150152 (7) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 August 29, 1988 NRC INFORMATION NOTICE NO. 88-70: CHECK VALVE INSERVICE TESTING PROGRAM
DEFICIENCIES
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is being provided to alert addressees to potential
problems uncovered by recent inspections of the check valve inservice testing
(IST) programs at Wm. B. McGuire Nuclear Station, Units 1 and 2 (McGuire),
Zion Nuclear Plant, Units 1 and 2 (Zion), and R. E. Ginna Nuclear Power
Plant (Ginna). It is expected that recipients will review the information
for applicability to their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information
notice do not constitute NRC requirements; therefore, no specific action or
written response is required.
Background:
During November 30 to December 11, 1987, and January 4 to 8, 1988, a diagnostic
inspection was performed at McGuire by a team led by personnel from the Office
for Analysis and Evaluation of Operational Data. The major inspection findings
pertaining to check valves were as follows:
(1) Check valves located in the steam supply line to the turbine-driven
auxiliary feedwater (AFW) pump were not included in the McGuire IST
program.
(2) AFW system valves, which include both isolation and check valves
used to isolate the three sources of non-safety-related water to
the AFW system, were not included in the McGuire IST program. The
non-safety-related water sources include the hot well, the AFW'
condensate storage tank, and the upper surge tanks.
(3) No reverse-flow operability tests were being performed on check
valves other than those valves used for containment isolation and
reactor coolant system pressure boundary isolation. This omission
112 A/e
IN 88-70
August 29, 1988 disregardsSection XI of the ASME Boiler and Pressure Vessel Code
(ASME code), which requires testing in the open or closed position
(or both), as necessary, to verify the valve's safety function.
Consequently, undetected check valve failures could have existed
because of the lack of testing.
From September 14 to 18, 1987, an inspection team performed a special check
valve inspection at Zion. Many check valves in the AFW system, the component
cooling water system, the chemical and volume control system, the diesel cooling
water system, and the feedwater system were found to be not included in the IST
program. Other major inspection findings were as follows:
(1) Pressure isolation valves (PIVs) were not being adequately tested
individually as required by an NRC confirmatory order issued
February 29, 1980.
(2) Valve testing did not ensure thdt all safety functions could be
accomplished.
(3) Test procedures did not result in valid tests of all valves listed as
having been tested in accordance with the ASME code.
(4) Valves failing leak-rate testing were not being repaired before re- start, contrary to commitments made in a June 11, 1987, response to
Generic Letter 87-06, "Periodic Verification of Leak-Tight Integrity
of Pressure Isolation Valves (PIYs)."
This inspection was followed by a special safety inspection on PIVs at Zion, which was performed between September 21 and October 26, 1987. Major in- spection findings were as follows:
(1) Zion procedures did not provide adequate leak tests for certain
check valves in the safety injection system.
(2) Test procedures failed, in some cases, to provide a viable means
to determine the actual leak rate. In other cases, a viable means
existed, but the licensee failed to calibrate the measuring in- struments.
(3) Leaking valves had been left unrepaired since mid-1986.
As a result of this inspection, the NRC issued a Level III violation to the
Commonwealth Edison Company on January 4, 1988.
From May 16 to 20, 1988, an inspection team performed a special announced
inspection on the IST activities at Ginna. The major inspection findings
pertaining to check valves-were as follows:
IN 88-70
August 29, 1988 in the
(1) Certain check valves in the main feedwater (MFW) system and in the
turbine-driven AFW pump steam supply lines were not included
Ginna IST program.
AFW
(2) A check valve in the steam supply line to the turbine-driven and
pump was found by the inspection team to have serious binding
full- to be in need of repair. If this valve had been undergoing
stroke exercising and reverse-flow closure testing, this failure
would not have gone undetected.
(3) Numerous check valves in the service water system, the containment
spray line, the residual heat removal system, the safety injection
(SI) system, and the SI accumulator discharge line were not being
full-stroke exercised.
for
(4) Certain check valves in these systems were not being tested
ASME code
reverse-flow closure capability in accordance with the
requirements.
to the
As a result of this inspection, the NRC issued a Level III violation
Rochester Gas and Electric Company on July 27, 1988.
Generating Sta- Similar problems were also discovered at the San Onofre NuclearNovember 21, 1985 tion Unit 1 (SONGS 1) when a serious water hammer occurred on
trip be- in the MFW system. This water hammer event occurred after a reactorline that had
cause of injection of auxiliary feedwater into a main feedwater Notice
partially drained through multiple inoperable check valves. Information
Feedwater System
86-01, "Failure of Main Feedwater Check Valves Causes Loss of
this
Integrity and Water-Hammer Damage," was issued to call attention to
incident.
Discussion:
The common findings from these inspections are as follows:
(1) Not all safety-related check valves have been identified and included
in the IST programs.
(2) When check valves are included in the program, the valves are not
always tested in a way that verifies their ability to perform their
safety-related functions.
the
These findings point out the importance of verifying the completeness of of
list of components included in IST programs and of ensuring the adequacy
the actual testing being performed when developing an IST program. Not taking
these two factors into account could result in undetected serious degradation is an
of components, as happened at SONGS 1 and Ginna. The incident at SONGS 1 example of the possible consequences of such degradation.
IN 88-70
August 29, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
C~ar
1-A 4 ~tSsr
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Horace K. Shaw, NRR
(301) 492-0906 Attachment: List of Recently Issued NRC Information Notices
Attachment
IN 88-70
August 29, 1988 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
88-69 Movable Contact Finger 8/19/88 All holders of OLs
Binding in HFA Relays or CPs for nuclear
Manufactured by General power reactors.
Electric (GE)
88-48, Licensee Report of Defective 8/24/88 All holders of OLs
Supplement 1 Refurbished Valves or CPs for nuclear
power reactors.
88-68 Setpoint Testing of Pres- 8/22/88 All holders of OLs
surizer Safety Valves with or CPs for nuclear
Filled Loop Seals Using power reactors.
Hydraulic Assist Devices
88-67 PWR Auxiliary Feedwater Pump 8/22/88 All holders of OLs
Turbine Overspeed Trip or CPs for nuclear
Failure power reactors.
88-66 Industrial Radiography 8/22/88 All NRC industrial
Inspection and Enforcement radiography licensees.
88-65 Inadvertent Drainages of 8/18/88 All holders of OLs
Spent Fuel Pools or CPs for nuclear
power reactors and
fuel storage facilities.
88-64 Reporting Fires in Nuclear 8/18/88 All holders of OLs
Process Systems at Nuclear or CPs for nuclear
Power Plants power reactors.
88-63 High Radiation Hazards 8/15/88 All holders of OLs
from Irradiated Incore or CPs for nuclear
Detectors and Cables power reactors, research reactors
and test reactors.
88-62 Recent Findings Concerning 8/12/88 All holders of NRC
Implementation of Quality quality assurance
Assurance Programs by program approval
Suppliers of Transport for radioactive
Packages material packages.
OL = Operating License
CP = Construction Permit
IN 88-70
August 29, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Horace K. Shaw, NRR
(301) 492-0906 Attachment: List of Recently Issued NRC Information Notices
- Transmitted by memo to Carl Berlinger from I.edyard Marsh dated August 25, 1988 -
- SEE PREVIOUS CONCURRENCES
CE,<X~ i 97K[t *C/OGCB:DOEA:NRR *RPB:ARM
CHBerlinger
NRR0 08/18/88 TechEd
08/12/88
- OGCB:DOEA:NRR *EMEB:DEST:NRR *EME1:DEST:NRR *EMEB:DEST:NRR *EAD/DEST:NRR
RJKiessel HShaw ESullivan LBMarsh JRichardson
08/11/88 08/02/88 08/02/88 08/25/88 08/18/88
- i m.
IN 88-XX
August xx, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or theftegional $ministrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Horace K. Shaw, NRR
(301) 492-0906 Attachment: List of Recently Issued NRC Information Notices
- Transmitted by memo to Carl Berlinger from Ledyard Marsh dated l ! a2s5 a via 1%92 D/DOEA:NRR C/OGCB:DOEA:NRR RPB:ARM
CERossi CHBerlinger TechEdZ42r
08/ /88 08/ /88 08//2/88 OGCB: EA:NRR *EMEB:DEST:NRR *EMEB:DEST:NRR *EMEB:DEST:NRR EAD/DEST:NRR
RJKiessel HShaw ESullivan LBMarsh JRichardson
08/;j /88 08/02/88 08/02/88 08/25/88 08/ /88
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list | - Information Notice 1988-01, Safety Injection Pipe Failure (27 January 1988, Topic: Unidentified leak, Water hammer)
- Information Notice 1988-03, Cracks in Shroud Support Access Hole Cover Welds (2 February 1988, Topic: Stolen)
- Information Notice 1988-04, Inadequate Qualification and Documentation of Fire Barrier Penetration Seals (5 February 1988, Topic: Fire Barrier, Fire Watch, Stolen)
- Information Notice 1988-05, Fire in Annunciator Control Cabinets (12 February 1988, Topic: Stolen)
- Information Notice 1988-06, Foreign Objects in Steam Generators (29 February 1988, Topic: Stolen)
- Information Notice 1988-07, Inadvertent Transfer of Licensed Material to Uncontrolled Locations (7 March 1988, Topic: Stolen)
- Information Notice 1988-08, Chemical Reactions with Radioactive Waste Solification Agents (14 March 1988, Topic: Process Control Program, Stolen)
- Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors (18 March 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) (23 December 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-11, Potential Loss of Motor Control Center And/Or Switchboard Function Due to Faulty Tie Bolts (7 April 1988)
- Information Notice 1988-12, Overgreasing of Electric Motor Bearings (12 April 1988)
- Information Notice 1988-13, Water Hammer & Possible Piping Damage Caused by Misapplication of Kerotest Packless Metal Diaphragm Globe Valves (18 April 1988)
- Information Notice 1988-14, Potential Problems with Electrical Relays (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (FDA) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (Fda) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-16, Identify Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities (22 April 1988, Topic: Water hammer)
- Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. (22 April 1988, Topic: Safe Shutdown, Weld Overlay, Feedwater Heater, Through-Wall Leak, Water hammer)
- Information Notice 1988-18, Malfunction of Lockbox on Radiography Device (25 April 1988, Topic: Overexposure)
- Information Notice 1988-19, Questionable Certification of Class Ie Components (26 April 1988, Topic: Water hammer)
- Information Notice 1988-19, Questionable Certification of Class IE Components (26 April 1988)
- Information Notice 1988-20, Unauthorized Individuals Manipulating Controls and Performing Control Room Activities (5 May 1988)
- Information Notice 1988-21, Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants (9 May 1988, Topic: Shutdown Margin)
- Information Notice 1988-22, Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations (12 May 1988)
- Information Notice 1988-23, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-Of-Coolant Accident (12 May 1988)
- Information Notice 1988-24, Failures of Air-Operated Valves Affecting Safety-Related Systems (13 May 1988)
- Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts (16 May 1988, Topic: Earthquake)
- Information Notice 1988-26, Falsified Pre-Employment Screening Records (16 May 1988)
- Information Notice 1988-27, Deficient Electrical Terminations Identified in Safety-Related Components (18 May 1988)
- Information Notice 1988-28, Potential for Loss of Post-Loca Recirculation Capability Due to Insulation Debris Blockage (19 May 1988, Topic: Coatings)
- Information Notice 1988-29, Deficiencies in Primary Containment Low-Voltage Electrical Penetration Assemblies (24 May 1988)
- Information Notice 1988-30, Target Rock Two-State SRV Setpoint Drift Update (25 May 1988)
- Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency (25 May 1988)
- Information Notice 1988-32, Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material (25 May 1988)
- Information Notice 1988-33, Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device (27 May 1988)
- Information Notice 1988-34, Nuclear Material Control & Accountability of Non-Fuel Special Nuclear Material at Power Reactors (31 May 1988)
- Information Notice 1988-36, Possible Sudden Loss of RCS Inventory During Low Coolant Level Operation (8 June 1988)
- Information Notice 1988-37, Flow Blockage of Cooling Water to Safety System Components (14 June 1988, Topic: Ultimate heat sink)
- Information Notice 1988-38, Failure of Undervoltage Trip Attachment of General Electric Circuit Breakers (15 June 1988)
- Information Notice 1988-39, Loss of Recirculation Pumps with Power Oscillation Event (15 June 1988)
- Information Notice 1988-40, Examiners' Handbook for Developing Operator Licensing Examinations (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (RERs) (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (Rers) (22 June 1988)
- Information Notice 1988-42, Circuit Breaker Failures Due to Loose Charging Spring Motor Mounting Bolts (23 June 1988, Topic: Loctite)
- Information Notice 1988-43, Solenoid Valve Problems (23 June 1988, Topic: Stroke time)
- Information Notice 1988-44, Mechanical Binding of Spring Release Device in Westinghouse Type DS-416 Circuit Breakers (24 June 1988)
- Information Notice 1988-45, Problems in Protective Relay & Circuit Breaker Coordination (7 July 1988, Topic: Safe Shutdown)
- Information Notice 1988-46, Licensee Report of Defective Refurbished Circuit Breakers (8 July 1988)
- Information Notice 1988-47, Slower-than-Expected Rod-drop Times (14 July 1988)
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