Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems| ML031140228 |
| 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, 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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  |
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| Issue date: |
04/24/1990 |
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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-90-026, NUDOCS 9004180107 |
| Download: ML031140228 (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, 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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane |
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Category:NRC Information Notice
[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 [[: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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>. |
- v
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 24, 1990
NRC INFORMATION NOTICE NO. 90-26: INADEQUATE FLOW OF ESSENTIAL SERVICE WATER
TO ROOM COOLERS AND HEAT EXCHANGERS FOR
ENGINEERED SAFETY-FEATURE SYSTEMS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is intended to alert addressees to potential problems
resulting from using the wrong flow and pressure drop relationship in estab- lishing adequate flow of essential service water to room coolers for engineered
safety-feature systems and from failing to establish or maintain balanced flows
in essential service water systems. 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.
Description of Circumstances
On March 9, 1990, the reactor at the Clinton Power Station was in cold shutdown, and the licensee was taking action to implement the recommendations contained
in Generic Letter 89-13, "Service Water System Problems Affecting Safety-Related
Equipment." The licensee discovered that the flow of essential service water
being supplied to several room coolers serving safety-related equipment was
approximately half of the design flow. The safety-related equipment included
components in the high-pressure and low-pressure core spray systems, the low- pressure injection system, the residual heat removal system, the standby gas
treatment system, the combustible gas control system, and the nuclear protection
system. After discovering the problem, the licensee declared these systems to
be inoperable. The room coolers were supplied to the Clinton Power Station by
American Air Filter, a subsidiary of Snyder General Corporation.
Before initial operation of the Clinton Power Station, the licensee obtained
the relationship of the flow and pressure drop on the water side of the room
coolers from the supplier. Plant personnel adjusted valving to establish the
pressure drop across each room cooler which would provide the design flow.
Plant personnel did not actually measure the flow to each room cooler.
IN 90-26 April 24, 1990 On March 9, 1990, the licensee discovered that the relationship between flow
and pressure drop for the room coolers was wrong and that flows of essential
service water to the room coolers were too low. Subsequently, the licensee
also found that the flows of essential service water to several other coolers
and heat exchangers were too low.
To balance the flow of essential service water through the system, plant
personnel measured the flow using qualified instrumentation and adjusted
flows to the room coolers according to these measurements. In some instances, the adjusted flows to specific components were somewhat less than design flows.
However, the licensee is performing analyses to determine whether these flows
are acceptable. Modifications to the updated final safety analysis report
will be submitted as necessary.
Discussion:
American Air Filter has supplied room coolers to approximately 50 nuclear
power plants including the Clinton Power Station. The room coolers consist
of bundles of folded tubes with supply and return headers at the ends of the
tubes. American Air Filter supplies the room coolers either with or without
pairs of cleanout plugs at the bends in the tubes. At design flow, room
coolers with cleanout plugs have a significantly greater pressure drop across
the tube bundle than room coolers without cleanout plugs.
On April 3, 1990, Illinois Power Company, licensee for the Clinton Power
Station, stated in a report submitted to NRC under 10 CFR 21.21 that pressure
drop data provided by American Air Filter for 22 of 23 room coolers was incor- rect. Twenty-two room coolers had cleanout plugs while the 23rd room cooler
did not. On April 5, 1990, Illinois Power Company submitted a licensee event
report which indicated that actual flows for the room coolers with cleanout
plugs ranged from 10 percent to 80 percent less than the design flows.
The licensee event report also indicated that 7 of 25 cooling components pro- vided by vendors other than American Air Filter and connected to the essential
service water system had flows that were less than the design flows. For these
cooling components, actual flows ranged from 2 percent to 42 percent less than
the design flows. The components include: two residual heat removal (RHR) heat
exchangers supplied by General Electric Company, two RHR pump seal coolers sup- plied by Byron Jackson, a switchgear heat removal condenser supplied by Carrier
Corporation, a fuel pool cooling and cleanup heat exchanger supplied by Yuba
Heat Exchanger, and a standby gas treatment system radiation monitor cooler
supplied by Sentry Equipment Corporation. Other components served by the
essential service water system were receiving excess flow. These flows ranged
up to 213 percent more than design flows.
Failure to properly balance flows of essential service water during pre- operational testing or failure to maintain balanced flows can lead to
degradation of safety-related equipment.
- %hWJ IN 90-26 April 24, 1990 This information notice requires 'no specific action or written response.
you have questions about the information in this notice, please contact theIf
technical contact listed belowlor the appropriate NAR project manager.
Ear es E. Ross ,Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment: List of Recently Issued NRC Information Notices
' ttaehment
April 24, 1990 LIST OF RECENTLY ISSUED
NRCINFORMATION NOTICES
f r- i*. Ato ot
Notice No. Subject Issuance Issued to
90-25 Loss of Vital AC Power 4/16/90 All holders, of OLs
with Subsequent Reactor or CPs for nuclear
Coolant System Neat-Up power reactors.
90-24 Transportation of Model 4/10/90 All NRC licensees
Spec 2-T Radiographic authorized to use, Exposure Device transport, or operate
devices and source
changers.
90-23 Improper Installation of 4/4/90 All holders of OLs
Patel Conduit Seals or CPs for nuclear
power reactors.
90-22 Unanticipated Equipment 3/23/90 All holders of OLs
Actuations Following or CPs for nuclear
Restoration of Power power reactors.
to Rosemount Transmitter
Trip Units
90-21 Potential Failure of Motor- 3/22/90 All holders of OLs
Operated Butterfly Valves or CPs for nuclear
to Operate Because Valve power reactors.
Seet Friction was Under- estimated
90-20 Personnel Injuries Resulting 3/22/90 All NRClicensees
froi Improper Operation of who process or
Radwaste Incinerators incinerate radio- active waste.
90-19 Potential Loss of Effective 3/14/90 All holders of OLs
Volume for Containment or CPs for PWRs.
Recirculation Spray at
PWRFacilities
90-18 Potential Problems with 3/9/90 All holders of OLs
Crosby- Safety-fls- or CPs-fo-nuc.ar-.
Used on Diesel Generator power reactors.
Air Start Receiver Tanks
OL
CP
FIRST CLASS MAIL
UNITED STATES POSTAGE
NUCLEAR REGULATORY COMMISSION USNRC
WASHINGTON, D.C. 20556 PERMIT No. 097 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
IN 90-26 April 24, 1990 This information notice requires no specific action or written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS PAGE FOR CONCURRENCE
- EAB:NRR *TECH EDITOR *EAB:NRR *PM:PD32:NRR *C:RVIB *C:PB3:RIII
RWoodruff BCalure PBaranowsky JHickman WBrach RKnop
4/10/90 4/10/90 4/12/90 4 10/90 4/12/90 4/12/90
PSwetland
4/13/90
CBerlinger
4/17/90 4//P90
z
NRCIN 90-XX
April XX, 1990 This information notice requires no specific action or written response. If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment: List of Recently Issued NRC Information Notices
CONCURRENCE:
- EAB:NRR *TECH EDITOR *EAB:NRR *R4:PD32:NRR *C:RVIB *CBPB3:RIII
RWoodruff BCalure PBaranowsky JHickman WBrach RKnop
4/10/90 4/ /90 4/ /90 4/ /90 4/ /90 4/ /90
PSwetland CBerlinger CERossi
4/ /90 4/(7/90 4/ /90
- See previous copy for concurrences
310c.in
NRCIN 90-XX
April XX, 1990 No specific action or written response is required by this information
notice. If you have 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:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment: List of Recently Issued Information Notices
FOCURENCE: IT'vYalnq 9 4 EEB: NRRl TECH EDITOR PM:PD32: C:PB3:RIII
PWoodruff - owsky RKnop
4/10/ 0 4/P0/90 4//190 4/10/90 1- o0 4/17./90
C: OGCB: NRR D:DOEA:NRR
Eltland CBerlinger CERossi
4/%*)/90 4/ /90 4/ /90
310b. in
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| list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Notice of Violation, Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Stress corrosion cracking, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Intergranular Stress Corrosion Cracking, Dissimilar Metal Weld, Exclusive Use)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990, Topic: Siren)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits, Stress corrosion cracking)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link, Siren)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990, Topic: Siren)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990, Topic: Loss of Offsite Power, Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
... further results |
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