Diesel Generator Fails Test Because of Degraded Fuel| ML031140351 |
| 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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
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| Issue date: |
01/16/1987 |
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| From: |
Jordan E NRC/IE |
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| To: |
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| References |
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| IN-87-004, NUDOCS 8701140224 |
| Download: ML031140351 (5) |
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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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, 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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] OR [[:Crane]] </code>. |
SSINS No.: 6835 IN 87-04
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
January 16, 1987
IE INFORMATION NOTICE NQ. 87-04:
DIESEL GENERATOR FAILS TEST BECAUSE
OF DEGRADED FUEL
I
I
Addressees
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This notice is to alert recipients to a potentially significant problem per- taining to long-term storage of fuel for diesel engines for emergency service.
This problem highlights the importance of a carefully structured inspection, sampling, and test program to verify continuing acceptability of the fuel for
emergency use. The NRC expects that recipients will review this notice for
applicability 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.
Reference
Documents:
1. Licensee Event Report No. 50-368/86-14, "Emergency Diesel
Generator Failure Due to Fuel Supply System Fouling as a
Result of Fuel Oil Degradation," November 18, 1986
2. , IE Circular No. 77-15, "Degradation of Fuel
Emergency Diesel Generator," November 23,
Oil Flow to the
1977
Description of Circumstances
On June 27, 1986, at Arkansas Nuclear One Unit 2 (ANO 2), one of the two
emergency diesel generators (EDGs) failed to complete a prescribed 24-hour
endurance test because of fuel starvation (Reference 1).
The licensee found
the screen element in the Y-strainer between the day tank and the engine
severely fouled (component B in Figure 1), restricting flow of fuel to the
engine.
Cleaning the element required using a hand-held torch to remove a hard
carbonaceous coating. The licensee cleaned the tank and piping and success- fully completed the endurance test.
PM
T..A
g9oia0 (
)ol4Ce 8760
IN 87-04 January 16, 1987 The corresponding strainer for the redundant EDG was found to not be as
severesy fouled.
The redundant EDG successfully performed a 24-hour endurance
test begun after the faulted EDG was made operable.
Discussion:
The licensee vi-ually inspected and cleaned the fuel supply system for each EDG
as short-term corrective action.
In addition, the licensee installed temporary
piping, pumps, and filters to recirculate and clean the fuel inventory.
The
interior surfaces of the day tanks and underground vault tanks had coatings of
sludge that were easily removed.
The fuel suction line foot valves and
strainers (component A in Figure 1) did not appear to be fouled.
During the evaluation of the event, the licensee determined that the day tank
strainers (components A and B in Figure 1) had not been routinely inspected and
cleaned because the station procedures did not address this action. Althoughi
these components are identified on the fuel supply system piping drawings, they
had not been considered in station procedures.
The licensee also determined
that the function of the component B strainers was adequately served by the
engine mounted strainers (Cuno-type; component C in Figure 1), which are
capable of removing particulates smaller than the rated removal size of the
component B strainers and are readily cleaned in service.
In addition, the
Cuno-type strainers are equipped with differential pressure indication.
Subsequently, in accordance with 10 CFR 50.59, the licensee removed the screen
element from the component B strainers for both EDGs.
The licensee engaged a contract laboratory to analyze the fuel.
The contractor
reported that a high concentration of particulates existed in the fuel as a
result of oxidation and biological contamination.
The licensee instituted a
program to enhance fuel quality by periodic inspection and cleaning of the
storage tanks and frequent sampling of the fuel.
The laboratory strongly
recommended use of a proprietary additive to prevent oxidation and to inhibit
biological growth; however, a decision has not been made on the use of any
additive.
Further, the licensee is considering design modifications to include
dual filters and strainers and a permanent storage tank recirculation system to
facilitate filtering of the complete inventory each refueling outage.
It should
Unit 2 in
_
on.-
be noted that the fuel supply systems differed between uniVL . alu
the absence on Unit 1 of the day tank strainers (components A and B
in riyur.:s}
On July 14, 1977, at Cooper, a clogged strainer had caused an EDG to similarly
starve of fuel oil.
This event was described and discussed in Reference 2.
IN 87-04 January 16, 1987 No specific action or written response is required by this information notice.
If YOu have any questions about this matter, please contact tfie Regicnal
Admnistrator of the appropriate regional office or this office.
Edward
fJoroin, Director
Divisi qn/of mergency Preparedness
and q~g neering Response
Office of lnspection and Enforcement
Technical Contacts:
Vern Hodge, IE
(301) 492-7275
Jim Henderson, IE
(301) 492-9654 Attachments:
1. F9gure 1 - Schematic Fuel Supply System for Emergency
Diesel Generator at Arkansas 2
2. List of Recently Issued IE Information Notices
-
-
-
-
-
-
-
-
-
-
-
--
- I
i
TYPICAL
l_INJECTOR l_MICRON
I
FILTER
100 MESH
l2 Y-STRAINER
I
II
N- -I
SRAINER
LDRAINl
U
l
$~
TO DAY TANK
IE
.NK
SAMPLE
EABOVE BOTTOM
TRANSFER PUMP
-DIESEL
ENGINE0
F fUEL PUMP
SKID
L
L____
S-
--
-
--
40 MESH
Y-STRAINER
Figure 1. Schematic Fuel Supply System for Emergency Diesel
Attachment 2
IN 87-04
January 16, 1987
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Infoin~ati on
Date of
Notice No.
Subject
Issue
Issued to
87-03 Segregation of Hazardous
1/15/87
All NRC licensees
87-02
87-01
86-110
86-109
86-108
86-107
86-106
86-105
86-104 Inadequate Seismic Quali- fication of Diaphragm
Valves by Mathematical
Modeling and Analysis
RHR Valve Misalignment
Causes Degradation of
Anomalous Behavior of
Recirculation Loop Flow
in Jet Pump BWR Plants
Diaphragm Failure In Scram
Outlet Valve Causing Rod
Insertion
Degradation Of Reactor
Coolant System Pressure
Boundary Resulting From
Boric Acid Corrosion
Entry Into PWR Cavity With
Retractable Incore Detector
Thimbles Withdrawn
Feedwater Line Break
Potential For Loss Of
Reactor Trip Capability
At Intermediate Power
Levels
Unqualified Butt Splice
Connectors Identified In
1/15/87
116/87
12/31/86
12/29/86
12/29/86
12/29/86
12/16/86
12/19/86
12/16/86
All power reactor
facilities holding
an OL or CP
All PWR facilities
holding an OL or CP
All BwR facilities
holding an OL or CP
All BIR facilities
holding an OL or CP
All PwR 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 holders of OL or CP
for PWR or BWR
All pressurized and
boiling-water reactor
facilities holding
an OL or CP
OL = Operating License
CP = Construction Permit
|
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|
| list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid, Overspeed trip)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment, Loss of Offsite Power)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987, Topic: Loss of Offsite Power, Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband, Water hammer)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987, Topic: Water hammer)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987, Topic: Water hammer)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987, Topic: Basic Component)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987, Topic: Basic Component)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987, Topic: Commercial Grade)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume, Water hammer)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987, Topic: Water hammer)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987, Topic: Excess Flow Check Valve)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987, Topic: Inattentive)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987, Topic: License Renewal)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Reactor Vessel Water Level)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch, Overspeed)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling, Uranium Hexafluoride)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987, Topic: Commercial Grade, Basic Component)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding, Overexposure)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area, Overexposure)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
... further results |
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