Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems| ML031140228 |
| Person / Time |
|---|
| 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  |
|---|
| Issue date: |
04/24/1990 |
|---|
| From: |
Rossi C
Office of Nuclear Reactor Regulation |
|---|
| To: |
|
|---|
| References |
|---|
| IN-90-026, NUDOCS 9004180107 |
| Download: ML031140228 (7) |
|
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 |
|---|
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.
If you have questions
about the information
in this notice, please contact the 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 NRC INFORMATION
NOTICES-f r i*. Ato ot*sv?TS Notice No.90-25 90-24 90-23 90-22 90-21 90-20 90-19 90-18 Subject Loss of Vital AC Power with Subsequent
Reactor Coolant System Neat-Up Transportation
of Model Spec 2-T Radiographic
Exposure Device Improper Installation
of Patel Conduit Seals Issuance 4/16/90 4/10/90 4/4/90 Unanticipated
Equipment
3/23/90 Actuations
Following Restoration
of Power to Rosemount
Transmitter
Trip Units Potential
Failure of Motor- 3/22/90 Operated Butterfly
Valves to Operate Because Valve Seet Friction was Under-estimated Personnel
Injuries Resulting
3/22/90 froi Improper Operation
of Radwaste Incinerators
Potential
Loss of Effective
3/14/90 Volume for Containment
Recirculation
Spray at PWR Facilities
Issued to All holders, of OLs or CPs for nuclear power reactors.All NRC licensees authorized
to use, transport, or operate*radiographic
exposure devices and source changers.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All NRC licensees who process or incinerate
radio-active waste.All holders of OLs or CPs for PWRs.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
License CP
Permit UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20556 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 FIRST CLASS MAIL POSTAGE
- FEES PAID USNRC PERMIT No. 097 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 RWoodruff 4/10/90*C:EAB:NRR
PSwetland 4/13/90*TECH EDITOR BCalure 4/10/90*C:OGCB:NRR
CBerlinger
4/17/90*EAB:NRR *PM:PD32:NRR
PBaranowsky
JHickman 4/12/90 4 10/90 4// P90*C:RVIB WBrach 4/12/90*C:PB3:RIII
RKnop 4/12/90
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 RWoodruff 4/10/90*C:EAB:NRR
PSwetland 4/ /90*TECH EDITOR BCalure 4/ /90 CBerlinger
4/(7/90*EAB:NRR PBaranowsky
4/ /90*R4:PD32:NRR
JHickman 4/ /90*C:RVIB WBrach 4/ /90*CBPB3:RIII
RKnop 4/ /90 D:DOEA:NRR
CERossi 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 (301)W. Woodruff, NRR 492-1180 Attachment:
List of Recently Issued Information
Notices FOCURENCE:
EEB: NRRlPWoodruff
-4/10/ 0 Eltland 4/%*)/90 IT'v Yalnq 9 TECH EDITOR 4/ P0/90 C: OGCB: NRR CBerlinger
4/ /90 owsky 4//190 D:DOEA:NRR
CERossi 4/ /90 PM: 4 PD32: 4/10/90 1-o0 C:PB3:RIII
RKnop 4/17./90 310b. in
|
|---|
|
| 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 |
|---|