Safety System Problems Caused by Modifications That Were Not Adequately Reviewed and TestedML031200373 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
09/03/1992 |
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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-92-065, NUDOCS 9208280105 |
Download: ML031200373 (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, 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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 [[: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 [[: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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
v)
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION_
WASHINGTON, D.C. 20555 6 September 3, 1992 -
7 '
NRC INFORMATION NOTICE 92-65: SAFETY SYSTEM PROBLEM flCAUSED BY MODIFICATIONS
THAT WERE NOT ADEQUATE-V REVIEWED AND TESTED
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to problems caused by inadequate review and testing
of safety system modifications. 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 are not NRC requirements; therefore, no specific
action or written response is required.
Description of Circumstances
The following describes two examples of safety system design errors that went
undetected since construction, because design changes were not thoroughly
reviewed and tested.
On October 10, 1991, during post overhaul testing, personnel at Arkansas
Nuclear One, Unit 1, observed that one of the high-pressure safety injection
(HPSI) pumps was losing its lubricating oil at a rate of more than 15 gallons
per hour as a result of oil spraying from the bearings. The licensee found
that the oil would always leak at this 'rate during emergency operation because
of excessive oil pressure caused by the simultaneous operation of two oil -
pumps that-served the HPSI pump. This condition had-existed since the plant
began operation.
The bearings for each of the HPSI pumps are supplied with lubricating oil by
two oil pumps, one attached directly to the HPSI pump itself and the other a
separate electric backup pump. Originally the electric oil pumps were
intended to be used during start up of a HPSI pump or to replace a
malfunctioning attached oil pump. The electric oil pumps could be started
manually and would start automatically when the oil pressure decreased below a
certain point. The licensee continues to use this method of control when the
HPSI pumps are used for normal reactor water makeup. However, during
construction, the licensee decided that the HPSI pumps would be more reliable
if the electric lubricating oil pumps ran continuously during emergency
operation. Consequently, the licensee modified the emergency controls to keep
9208280105 ?DR J4E fltc6-S-O
c a0 7 0-3 WI
IN 92-65 September 3, 1992 the electric oil pumps-operating whenever an emergency safety features
actuation system (ESFAS) signal was present. Anticipating that the
simultaneous operation of both oil pumps could cause excessive oil pressure, the licensee added an oil- pressure relief valve to the oil system. However, the relief valve settings were not appropriately selected to prevent oil
spraying from the bearings.
In September 1991, the Gulf States Utilities Company, licensee for the River
Bend Station, discovered that the outlet valves for the hydrogen mixing system
would immediately close if an operator attempted to start up the system by
opening these valves when a loss-of-coolant accident (LOCA) signal was
present. An interlock prevented the mixing system fans from operating with
the outlet valves closed. Consequently, the hydrogen mixing system would have
been inoperable if a LOCA signal were present. This condition had existed
since the plant was constructed.
The River Bend Station is a boiling water reactor with a Mark III containment
structure. This containment structure consists of two chambers, a large outer
primary containment and a drywell which is inside the primary containment and
surrounds the reactor vessel. This system suppresses the steam pressure
released during a LOCA by directing the steam through the suppression pool
water into the primary containment. After the initial pressure suppression is
complete following a LOCA, hydrogen created by the zirconium-water reaction
would be mainly concentrated in the drywell. The hydrogen mixing system is
provided to reduce the concentration of the hydrogen in the drywell by moving
it into the primary containment where it is diluted and reduced in
concentration by the hydrogen recombiners.
The redundant hydrogen mixing systems each have two lines penetrating the
drywell; an outlet line having a recirculating fan to draw suction from the
drywell and an inlet line that allows diluted air to reenter the drywell.
Each of these lines has two isolation valves which are normally closed during
plant operation. In 1983, during construction, the licensee added a LOCA
interlock to the hydrogen mixing system that would automatically close all
eight of the mixing system valves upon receiving a LOCA signal. In 1984, the
licensee revised the control logic for the mixing system valves to
automatically override a LOCA signal when the operator opened the drywell
inlet valves. However, the licensee did not provide this LOCA override
capability for the outlet line valves.
Discussion
In both of these cases, the licensee changed the design with the intention of
increasing the reliability of safety systems. However, because the licensees
did not adequately review and test the designs, these changes introduced
errors that could have prevented the systems from performing their safety
functions as intended.
At Arkansas Nuclear One, the licensee intended to increase the reliability of
the HPSI system by causing both HPSI oil pumps to operate simultaneously when
an ESFAS signal was present. However, the oil pumps had apparently never been
run simultaneously for any extended period untiltthe recent overhaul test.
IN 92-65 September 3, 1992 The licensee routinely conducted the' required periodic pump surveillance tests
with the HPSI operating in the normal-reactor makeup'mode with only one oil
pump running at a time. The licensee tested the effectiveness of the
ESFAS signal during each refueling outage. However, the test only required
verification that the test signal would actuate the HPSI system and did not
result in the simultaneous operation'of the two oil pumps for an extended
time. As a result, neither of these tests revealed the oil leakage problem.
The licensee estimated'that a HPSI 'pump would have performed satisfactorily
for only 80 minutes without-operator action to replenish the oil or to stop
the electric oil pumps. With an ESFAS signal present, the electric oil pumps
cannot be stopped from the control room,'but must be'stopped by opening local
power supply breakers.
The licensee has modified the oil pressure relief'valve settings to minimize
the oil leakage. Procedures were established that instruct the operators to
stop the electric oil pumps 15 minutes after an ESFAS actuation of the pumps.
At River Bend, the control logic to automatically close all of the mixing
system valves was provided to ensure that the drywell integrity would be
restored if a LOCA occurred during a mixing system test with the valves open.
Apparently, the LOCA override for the inlet valves was provided later to
permit the drywell to be depressurized to clear a false LOCA signal that might
be caused by a loss of offsite power. The false LOCA signal could be
generated by the drywell pressure rise that would accompany a loss of drywell
cooling. Since the drywell could be depressurized without opening the outlet
valves, the LOCA override was not provided for these valves. The need to open
the outlet to operate the hydrogen mixing was apparently not considered for
this change. Normal surveillance testing did not reveal this design error
because it was never conducted with a LOCA signal present.
When the licensee discovered this design error, it declared both hydrogen
mixing trains inoperable and commenced shutting down the reactor. The
licensee then developed a LOCA bypass procedure for the hydrogen mixing
system.
These events highlight the importance of thoroughly reviewing any safety- related design change, including considering the effect of the change on all
related systems. The events also show the need for completely testing the
systems affected by the design change under conditions that simulate as nearly
as possible those conditions that are expected to exist when the systems are
needed.
IN 92-65 September 3, 1992 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
-the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
harles E. Rossi, Director'
Division of-Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contact: Thomas F. Westerman, RIV
(817) 860-8145 Attachment: List of Recently Issued NRC Information Notices
V)Attachment
IN 92-65 September 3, 1992 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-64 Nozzle Ring Settings 08/28/92 All holders of OLs or CPs
on Low Pressure Water- for nuclear power reactors.
Relief Valves
92-63 Cracked Insulators in 08/26/92 All holders of OLs or CPs
ASL Dry Type Transformers for nuclear power reactors.
Manufactured by Westing- house Electric Corporation
92-62 Emergency Response 08/24/92 All U.S. Nuclear Regulatory
Information Require- Commission licensees.
ments for Radioactive
Material Shipments
92-61 Loss of High Head 08/20/92 All holders of OLs or CPs
Safety Injection for nuclear power reactors.
60 Valve Stem Failure 08/20/92 All holders of OLs or CPs
Caused by Embrittlement for pressurized water
reactors (PWRs).
92-59 Horizontally-Installed 08/18/92 All holders of OLs or CPs
Motor-Operated Gate for nuclear power reactors.
Valves
92-58 Uranium Hexafluoride 08/12/92 All Fuel Cycle Licensees.
Cylinders - Deviations
in Coupling Welds
92-57 Radial Cracking of- 08/11/92 All holders of OLs or CPs
Shroud Support Access for boiling water reactors
Hole Cover Welds (BWRs).
92-56 Counterfeit Valves in 08/06/92 All holders of OLs or CPs
the Commercial Grade for nuclear power reactors.
Supply System
92-55 Current Fire Endurance 07/27/92 All holders of OLs or CPs
Test Results for for nuclear power reactors.
Thermo-Lag Fire Barrier
Material
OL = Operating License
CP = Construction Permit
|
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|
list | - Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls (3 January 1992)
- Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation (3 January 1992)
- Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers (6 January 1992)
- Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures (6 January 1992, Topic: Probabilistic Risk Assessment)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays (8 January 1992)
- Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays (8 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications (15 January 1992)
- Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping (9 January 1992)
- Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents (23 January 1992)
- Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions (30 January 1992)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments (31 January 1992, Topic: Brachytherapy)
- Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities (5 February 1992, Topic: Brachytherapy)
- Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications (10 February 1992, Topic: Brachytherapy)
- Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites (18 February 1992, Topic: Brachytherapy)
- Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities (21 February 1992, Topic: Brachytherapy)
- Information Notice 1992-15, Failure of Primary Systems Compression Fitting (24 February 1992)
- Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown (25 February 1992, Topic: Reactor Vessel Water Level, Temporary Modification, Brachytherapy)
- Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 (26 February 1992, Topic: Stroke time)
- Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire (28 February 1992, Topic: Hot Short, Safe Shutdown)
- Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays (2 March 1992)
- Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays (2 March 1992)
- Information Notice 1992-20, Inadequate Local Leak Rate Testing (3 March 1992)
- Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations (24 March 1992)
- Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment (27 March 1992)
- Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays (30 March 1992)
- Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves (2 April 1992, Topic: Stroke time, Hydrostatic)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications (3 April 1992)
- Information Notice 1992-28, Inadequate Fire Suppression System Testing (8 April 1992, Topic: Safe Shutdown)
- Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry (17 April 1992)
- Information Notice 1992-30, Falsification of Plant Records (23 April 1992)
- Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers (27 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers (29 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed (30 April 1992)
- Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed (30 April 1992)
- Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor (6 May 1992)
- Information Notice 1992-36, Intersystem LOCA Outside Containment (7 May 1992)
- Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule (8 May 1992)
- Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (26 May 1992, Topic: Brachytherapy)
- Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown (13 May 1992, Topic: Fuel cladding)
- Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry (27 May 1992)
- Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust (29 May 1992, Topic: Anchor Darling)
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