Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater PumpsML031070374 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000370 |
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Issue date: |
07/09/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-93-051, NUDOCS 9307010233 |
Download: ML031070374 (12) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000370 |
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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 [[: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]] OR [[:05000370]] </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 [[: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]] OR [[:05000370]] </code>. |
r -UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 9, 1993 NRC INFORMATION
NOTICE 93-51: REPETITIVE
OVERSPEED
TRIPPING OF TURBINE-DRIVEN
AUXILIARY
FEEDWATER
PUMPS
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 the problem of repetitive
tripping of turbine-driven auxiliary
feedwater
pumps (TDAFWPs)
at the South Texas Project Electric Generating
Station. 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
On December 27, 1992, Houston Lighting & Power Company (the licensee)performed
a monthly surveillance
test on its Unit 1 TDAFWP. After receiving
a start signal, the pump immediately
tripped on an overspeed
condition.
The operators
repeated the surveillance
test after a successful
local manual start. On this attempt the pump successfully
started, and the licensee subsequently
considered
the pump operable.On January 23, 1993, Unit 2 tripped from 100-percent
power on low water level in one of the steam generators.
The trip occurred because electro-hydraulic
control oil to the steam generator
main feedwater
pump turbine was lost. The Unit 2 TDAFWP started on demand and was later secured when no longer required.After the pump was secured, problems occurred when operators
attempted
to relatch MOV-514 (the TDAFWP trip/throttle
valve) from the control room. (See Figure 1.) The pump was declared inoperable.
The licensee conducted
a significant
amount of troubleshooting
and testing on the TDAFWP to resolve the MOV-514 relatch problem and another speed control problem that was identified
during the testing. After the operability
surveillance
test was completed successfully, the TDAFWP was declared operable and the unit was restarted
on January 25, 1993.On January 28, 1993, the Unit 1 TDAFWP was tested as part of a routine monthly surveillance.
When started, the TDAFWP immediately
tripped on an overspeed condition
and was subsequently
declared inoperable.
From January 28 through 9307010233 P 9t PC w3 -oSI 9 15 I
-I IN 93-51 July 9, 1993 January 30, 1993, the licensee undertook
an extensive
testing and troubleshooting
effort to determine
the cause of the problem with the TDAFWP.Numerous pump starts were completed.
Several problems (overspeed
tripping, lack of speed control, oscillations, and inability
to maintain rated full-load, steady-state
speed) were identified.
On January 30, 1993, the Unit 1 TDAFWP was declared operable following
extensive
maintenance
activities
and the successful
completion
of the surveillance
test.On February 1, 1993, the Unit 1 TDAFWP was tested again at the direction
of the Unit 1 operations
manager in order to ensure operability, considering
the numerous problems encountered
previously.
After receiving
a start signal, the pump tripped on an overspeed
condition
and was declared inoperable.
On February 3, 1993, Unit 2 was operating
at 100-percent
power. Two steam-driven steam generator
main feedwater
pumps and one electric startup feedwater pump were providing
feed flow to the steam generators.
The startup feedwater pump tripped when the pump lubricating
oil duplex strainers
were being shifted. Operators
began to manually ramp down power but were unable to avoid the low steam generator
level. The operators
subsequently
initiated
a manual reactor trip before receiving
an automatic
reactor protection
system trip signal on low steam generator
level. Following
the plant trip, the Unit 2 TDAFWP received an automatic
signal to supply water to the steam generators.
The pump started but immediately
tripped on an overspeed
condition.
On February 4, 1993, Unit 1 commenced
a shutdown to place the reactor in the mode required by the Technical
Specifications
because the TDAFWP had not been restored to an operable condition
within the outage time allowed by the Technical
Specifications.
Further details can be found in License Event Report 50-498/93-007 and NRC Inspection
Reports 50-498; 50-499/93-05 and 50-498; 50-499/93-07.
Discussion
Although the licensee did not identify the root cause of the Unit 1 TDAFWP overspeed
trips, the proximate
cause was determined
to be the intrusion
of water into the TDAFWP turbine that adversely
affected its performance.
However, this cause was effectively
masked for several surveillance
tests because the surveillance
test program established
to satisfy the operability
requirements
of the Technical
Specifications
was not sufficiently
rigorous to assure that the testing was performed
under suitable environmental
conditions.
The TDAFWP was not returned to its normal standby condition
before each of the TDAFWP surveillance
tests performed
on December 27, 1992, and January 30, 1993. Because of this, the pump was not tested in its normal standby condition
and degraded conditions
affecting
operability
were not revealed.
IN 93-51 July 9, 1993 The licensee determined
that the root cause of the February 3, 1993, Unit 2 TDAFWP overspeed
trip was an incorrect
valve lineup in conjunction
with an Inoperable
or degraded steam trap. The valves and the steam trap are located in the drain line from the steam admission
line. (See Figure 1.) The TDAFWP overspeed
trip was caused by excessive
condensate
buildup in the steam supply line upstream of the trip/throttle
valve (MOV-514 in Figure 1). The excessive condensate
had accumulated
because the steam trap bypass valve, MS-517, was incorrectly
positioned (closed) and the steam trap had degraded to such an extent that it was no longer capable of passing condensate
to the condenser.
The licensee took the following
corrective
actions related to the hardware modifications
for both units:* The trip/throttle
valves and governors
were sent to the respective
vendors for complete refurbishment
and testing. The gearing arrangement
of the trip/throttle
valve was modified to ensure slower stroke time, thus enabling a more positive governor response.* The TDAFWP drain system was modified to remove the steam traps in the steamline
drain system, replacing
them with a spool piece. Also, the trip/throttle
valve high-pressure
steam leakoff was separated
from the turbine casing drain line and rerouted to the sump to prevent possible intrusion
of steam into the turbine casing. (See Figure 2.)Related Generic Communications
Notice 86-14, Supplement
2, "Overspeed
Trips of AFW, HPCI, and RCIC Turbines," dated August 26, 1991.* NRC Information
Notice 88-09, "Reduced Reliability
of Steam-Driven
Auxiliary
Feedwater
Pumps Caused by Instability
of Woodward PG-PL Type Governors," dated March 18, 1988.* IE Information
Notice 86-14, Supplement
1, "Overspeed
Trips of AFW, HPCI, and RCIC Turbines," dated December 17, 1986.* IE Information
Notice 86-14, "PWR Auxiliary
Feedwater
Pump Turbine Control Problems," dated March 10, 1986.
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachments:
1. Figure 1, Existing South Texas Project TDAFWP Steam Supply and Exhaust System 2. Figure 2, Modified South Texas Project TDAFWP Steam Supply and Exhaust System 3. List of Recently Issued NRC Information
Notices
MOV-143 STEAM EXHAUST LINE STEAM ADMISSION LINE MOV-514 TERRY TURBINE (STEAM ADMISSION LINE DRAIN VALVES PIPE CAP WITH ORIFICE If (UNIT I ONLY)MS 371 MS 370 FO 7537B~1 I I FO 7537A--Yl MS TURBINE CASING 373 DRAIN VALVE STEAM TRAP BYPASS VALVE STEAM TRAP w I1°% I'-(D% %D n 0D w I-a%0 r CONDENSER FIGURE 1 TDAFWP STEAM SUPPLY AND EXHAUST SYSTEM (UNMODIFIED)
MOV-143 STEAM EXHAUST LINE STEAM ADMISSION LINE MOV-514 TERRY TURBINE C STEAM ADMISSION UNE DRAIN VALVES MS 370 FO 7537B MS TURBINE CASING 373 DRAIN VALVE MS 515 STEAM TRAP BYPASS VALVE SPOOL PIECE m 'z--~HAQ %D t" MD3%O D" D Wa " MS 516 CONDENSER FIGURE 2 TDAFWP STEAM SUPPLY AND EXHAUST SYSTEM (MODIFED)
Attachment
3 IN 93-51 July 9, 1993 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 93-50 93-49 93-48 92-06, Supp. 1 93-47 Extended Storage of Sealed Sources Improper Integration
of Software into Operating Practices Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated
Oil Reliability
of ATWS Mitigation
Systems and Other NRC-Required
Equip-ment not Controlled
by Plant Technical
Specifica- tion Unrecognized
Potential
Problem with Westinghouse
Rod Control System and Inadvertent
Withdrawal
of A Single Rod Control Cluster Assembly Degradation
of Shutdown Cooling System Performance
Operational
Challenges
During A Dual-Unit Transient Use of Inappropriate
Lubrication
Oils in Safety-Related
Applications
07/08/93 07/08/93 7/6/93 07/01/93 06/18/93 6/10/93 06/16/93 06/15/93 06/10/93 All licensees
authorized
to possess sealed sources.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 holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for Westinghouse (W)-designed nuclear power reactors.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.93-46 93-45 93-44 93-43 OL = Operating
License CP -Construction
Permit
\,-IN 93-51 July 9, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.orig /s/'d by BKGrimes Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachments:
1. Figure 1, Existing South Texas Project TDAFWP Steam Supply and Exhaust System 2. Figure 2, Modified South Texas Project TDAFWP Steam Supply and Exhaust System 3. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB:DORS
- DRP:RIV *TECH ED. *SC:DRP:RIV
NAME PCWen/vsb
l MASatorius
MFMejac WDJohnson
ABBeach DATE 06/01/93 l 06/02/93 06/02/93 06/04/93 06/04/93*PM:PDV:NRR
D LEKokaJko
CEMcCracken
ACThadani
GHMarcus dd____06/08/93 06/09/93 06/10/93 06/16/93 DOCUMENT NAME: 93-51.IN
IN 93-xx June xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter (301)C. Wen, NRR 504-2832 Attachments:
1. Figure 1, Existing South Texas Project TDAFWP Steam System 2. Figure 2, Modified South Texas Project TDAFWP Steam System 3. List of Recently Issued NRC Information
Notices Supply and Exhaust Supply and Exhaust*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB:DORS
- DRP:RIV *TECH ED. *SC:DRP:RIV
N.ME PCWen/vsb
MASatorius
MFMejac WDJohnson
ABBeach DATE 06/01/93 06/02/93 06/02/93 06/04/93 06/04/93*PM:PDV:NRR
l *C:SPLB:DSSA:NRR
C:OGCB:DORS:NRR
D LEKokaiko
CEMcCracken
l ACThadani
GHMarcus( r lines 06/08/93 1 06/09/93 06/10/93 06//6/93 06/,z/93 DOCUMENT NAME: INTDAFWP.WP
6 IN 93-xx June xx, 1993 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachments:
1. Figure 1, Existing South Texas Project TDAFWP Steam Supply and Exhaust System 2. Figure 2, Modified South Texas Project TDAFWP Steam Supply and Exhaust System 3. List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB:DORS
- DRP:RIV *TECH ED. *SC:DRP:RIV
NAME PCWen/vsb
MASatorius
MFMejac WDJohnson
ABBeach DATE 06/01/93 06/02/93 06/02/93 06/04/93 06/04/93 PM PDV:NRR P e E BC:OGCB:DORS:NRR
D:DORS:NRR
LEKokaiko
CEMcCI J dThadani GHMarcus BKGrimes 06/1 /93 06/ "/93 06/f/L93 06/ /93 06/ /93 DOCUMENT NAME: INTDAFWP.WP
l
06-S12-1119
14t130..1 06/04/93 15:05;301 5 34 37 R I'J US NRC FTS 728-327'3 NRC WHZTEl LINT F 002 P.02 IN 93-xx Junt Xx, 1993 rhis iofwmtion
notice requires no specific act on or written response.
If yew ton & questions
about the information
in his notice, please contact*a of tochnical
contacts listed bolow or th appropriate
Office of btlw lector Regulation (NRR) project manager Toc"ial contatts: Brian K. Gripes, Director Division of OPerating
Reactor Support Office of Nuclear Reactor Regulation
MKrk A. Satorius, RI'(817) 660-4141 William D. Johnton, RIV (817) B6O-814B Peter C. Win NRR (301) 504-28i2 fttocwtsz:1
1. fig" It Existing South Texas Project TDAfWP Steam Supply 9 t 1. FlKrp 2, Modified South Texas Project TDA4I P Steam Supply S. stoe.ist tf Recently Issued NRC Information
Noice~s and Exhaust and Exhaust I Q2I fIaCURR E _.__ I___-(, 0 1 93 PCmn/sb tSu:D~ohnn
-/0ul __ 06/02/931
0/P3 OS .6 / .CttKn-ANtrRR
D OSZiARR 9C OCt!R!OOR$:tRR
De:nRS!NRR
-I ACHhadani
Marcus bKoritme U- a 0r:w : 1"TuAokIrP
IN 93-xx June xx, 1993 Page 3 of This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachment:
List of Recently Issued NRC Information
Notices_. __I OFFICE OGCB:DORS
DRP:RIV TECH ED. SC:DRP:RIV
D:DRP:RIV NAME PCWen/vsb
MASatorius
A. WDJohnson
ABBeach DATE .06/ I /93 _ 06/ /93 06/-L193 f06/ /93 l 06/ /93....BC:SPLB:DSSA:NRR
D:DSSA:NRR
BC:OGCB:DORS:NRR
D:DORS:NRR
CEMcCracken
ACThadani
GHMarcus BKGrimes 06/ /93 06/ /93 06/ /93 06/ /93 UMUWMMI NAMt: IN IUDAWFW. WF
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride, Inattentive)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993, Topic: Thermal fatigue)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay, Thermal fatigue)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993, Topic: Commercial Grade, Thermal fatigue)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure, Thermal fatigue)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993, Topic: Thermal fatigue)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993, Topic: Commercial Grade)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993, Topic: Water hammer)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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