Information Notice 1993-51, Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps: Difference between revisions

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{{#Wiki_filter:r -UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555July 9, 1993NRC INFORMATION NOTICE 93-51: REPETITIVE OVERSPEED TRIPPING OF TURBINE-DRIVENAUXILIARY FEEDWATER PUMPS
{{#Wiki_filter: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==
==Addressees==
All holders of operating licenses or construction permits for nuclear powerreactors.
All holders of operating
 
licenses or construction
 
permits for nuclear power reactors.


==Purpose==
==Purpose==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the problem of repetitive tripping of turbine-driven auxiliary feedwater pumps (TDAFWPs) at the South Texas Project ElectricGenerating Station. It is expected that recipients will review theinformation for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained inthis information notice are not NRC requirements; therefore, no specificaction or written response is required.
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
 
* NRC Information
 
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.
 
* .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.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
 
===Loss of Control Room Annunciators===
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
 
*D: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
 
*C:SPLB:DSSA:NRR
 
*D:DSSA:NRR
 
*C:OGCB:DORS: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
 
*D: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
 
*D: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
 
*D: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


==Description of Circumstances==
D:DRP:RIV NAME PCWen/vsb
On December 27, 1992, Houston Lighting & Power Company (the licensee)performed a monthly surveillance test on its Unit 1 TDAFWP. After receiving astart signal, the pump immediately tripped on an overspeed condition. Theoperators repeated the surveillance test after a successful local manualstart. On this attempt the pump successfully started, and the licenseesubsequently considered the pump operable.On January 23, 1993, Unit 2 tripped from 100-percent power on low water levelin one of the steam generators. The trip occurred because electro-hydrauliccontrol oil to the steam generator main feedwater pump turbine was lost. TheUnit 2 TDAFWP started on demand and was later secured when no longer required.After the pump was secured, problems occurred when operators attempted torelatch MOV-514 (the TDAFWP trip/throttle valve) from the control room. (SeeFigure 1.) The pump was declared inoperable. The licensee conducted asignificant amount of troubleshooting and testing on the TDAFWP to resolve theMOV-514 relatch problem and another speed control problem that was identifiedduring the testing. After the operability surveillance test was completedsuccessfully, the TDAFWP was declared operable and the unit was restarted onJanuary 25, 1993.On January 28, 1993, the Unit 1 TDAFWP was tested as part of a routine monthlysurveillance. When started, the TDAFWP immediately tripped on an overspeedcondition and was subsequently declared inoperable. From January 28 through9307010233 P 9t PC w3 -oSI 915I


-IIN 93-51July 9, 1993 January 30, 1993, the licensee undertook an extensive testing andtroubleshooting 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 1TDAFWP was declared operable following extensive maintenance activities andthe successful completion of the surveillance test.On February 1, 1993, the Unit 1 TDAFWP was tested again at the direction ofthe Unit 1 operations manager in order to ensure operability, considering thenumerous problems encountered previously. After receiving a start signal, thepump 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 feedwaterpump were providing feed flow to the steam generators. The startup feedwaterpump tripped when the pump lubricating oil duplex strainers were beingshifted. Operators began to manually ramp down power but were unable to avoidthe low steam generator level. The operators subsequently initiated a manualreactor trip before receiving an automatic reactor protection system tripsignal on low steam generator level. Following the plant trip, the Unit 2TDAFWP 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 themode required by the Technical Specifications because the TDAFWP had not beenrestored to an operable condition within the outage time allowed by theTechnical Specifications.Further details can be found in License Event Report 50-498/93-007 and NRCInspection Reports 50-498; 50-499/93-05 and 50-498; 50-499/93-07.DiscussionAlthough the licensee did not identify the root cause of the Unit 1 TDAFWPoverspeed trips, the proximate cause was determined to be the intrusion ofwater into the TDAFWP turbine that adversely affected its performance.However, this cause was effectively masked for several surveillance testsbecause the surveillance test program established to satisfy the operabilityrequirements of the Technical Specifications was not sufficiently rigorous toassure that the testing was performed under suitable environmental conditions.The TDAFWP was not returned to its normal standby condition before each of theTDAFWP surveillance tests performed on December 27, 1992, andJanuary 30, 1993. Because of this, the pump was not tested in its normalstandby condition and degraded conditions affecting operability were notrevealed.
MASatorius


IN 93-51July 9, 1993 The licensee determined that the root cause of the February 3, 1993, Unit 2TDAFWP overspeed trip was an incorrect valve lineup in conjunction with anInoperable or degraded steam trap. The valves and the steam trap are locatedin the drain line from the steam admission line. (See Figure 1.) The TDAFWPoverspeed trip was caused by excessive condensate buildup in the steam supplyline upstream of the trip/throttle valve (MOV-514 in Figure 1). The excessivecondensate had accumulated because the steam trap bypass valve, MS-517, wasincorrectly positioned (closed) and the steam trap had degraded to such anextent that it was no longer capable of passing condensate to the condenser.The licensee took the following corrective actions related to the hardwaremodifications for both units:* The trip/throttle valves and governors were sent to the respectivevendors for complete refurbishment and testing. The gearing arrangementof 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 thesteamline drain system, replacing them with a spool piece. Also, thetrip/throttle valve high-pressure steam leakoff was separated from theturbine casing drain line and rerouted to the sump to prevent possibleintrusion of steam into the turbine casing. (See Figure 2.)Related Generic Communications* NRC Information 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-DrivenAuxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL TypeGovernors," 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 TurbineControl Problems," dated March 10, 1986.
A. WDJohnson


* .IN 93-51July 9, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Mark A. Satorius, RIV(817) 860-8141William D. Johnson, RIV(817) 860-8148Peter C. Wen, NRR(301) 504-2832Attachments:1. Figure 1, Existing South Texas ProjectTDAFWP Steam Supply and Exhaust System2. Figure 2, Modified South Texas ProjectTDAFWP Steam Supply and Exhaust System3. List of Recently Issued NRC Information Notices
ABBeach DATE .06/ I /93 _ 06/ /93 06/-L193 f06/ /93 l 06/ /93....BC:SPLB:DSSA:NRR


MOV-143STEAM EXHAUSTLINESTEAM ADMISSIONLINEMOV-514TERRYTURBINE(STEAM ADMISSIONLINE DRAINVALVESPIPE CAP WITH ORIFICEIf (UNIT I ONLY)MS371MS370FO 7537B~1I IFO 7537A--YlMS TURBINE CASING373 DRAIN VALVESTEAM TRAPBYPASSVALVESTEAMTRAPw I1°% I'-(D% %D n0D wI-a%0 rCONDENSERFIGURE 1TDAFWP STEAM SUPPLY AND EXHAUST SYSTEM (UNMODIFIED)
D:DSSA:NRR
MOV-143STEAM EXHAUSTLINESTEAM ADMISSIONLINEMOV-514TERRYTURBINECSTEAM ADMISSIONUNE DRAINVALVESMS370FO 7537BMS TURBINE CASING373 DRAIN VALVEMS515STEAM TRAPBYPASSVALVESPOOLPIECEm 'z--~HAQ %D t" MD3%O D" DWa "MS516CONDENSERFIGURE 2TDAFWP STEAM SUPPLY AND EXHAUST SYSTEM (MODIFED)
Attachment 3IN 93-51July 9, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-5093-4993-4892-06,Supp. 193-47Extended Storage ofSealed SourcesImproper Integration ofSoftware into OperatingPracticesFailure of Turbine-Driven Main FeedwaterPump to Trip Because ofContaminated OilReliability of ATWSMitigation Systems andOther NRC-Required Equip-ment not Controlled byPlant Technical Specifica-tionUnrecognized Loss ofControl Room AnnunciatorsPotential Problem withWestinghouse Rod ControlSystem and InadvertentWithdrawal of A SingleRod Control Cluster AssemblyDegradation of ShutdownCooling System PerformanceOperational ChallengesDuring A Dual-UnitTransientUse of InappropriateLubrication Oils inSafety-Related Applications07/08/9307/08/937/6/9307/01/9306/18/936/10/9306/16/9306/15/9306/10/93All licensees authorizedto possess sealed sources.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor Westinghouse (W)-designed nuclear powerreactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.93-4693-4593-4493-43OL = Operating LicenseCP -Construction Permit


\,-IN 93-51July 9, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.orig /s/'d by BKGrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Mark A. Satorius, RIV(817) 860-8141William D. Johnson, RIV(817) 860-8148Peter C. Wen, NRR(301) 504-2832Attachments:1. Figure 1, Existing South Texas Project TDAFWPSteam Supply and Exhaust System2. Figure 2, Modified South Texas ProjectTDAFWP Steam Supply and Exhaust System3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB:DORS *DRP:RIV *TECH ED. *SC:DRP:RIV *D:DRP:RIVNAME PCWen/vsb l MASatorius MFMejac WDJohnson ABBeachDATE 06/01/93 l 06/02/93 06/02/93 06/04/93 06/04/93*PM:PDV:NRR *C:SPLB:DSSA:NRR *D:DSSA:NRR *C:OGCB:DORS:NRR DLEKokaJko CEMcCracken ACThadani GHMarcus dd____06/08/93 06/09/93 06/10/93 06/16/93DOCUMENT NAME: 93-51.IN
BC:OGCB:DORS:NRR


IN 93-xxJune xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Mark A. Satorius, RIV(817) 860-8141William D. Johnson, RIV(817) 860-8148Peter(301)C. Wen, NRR504-2832Attachments:1. Figure 1, Existing South Texas Project TDAFWP SteamSystem2. Figure 2, Modified South Texas Project TDAFWP SteamSystem3. List of Recently Issued NRC Information NoticesSupply and ExhaustSupply and Exhaust*SEE PREVIOUS CONCURRENCEOFFICE *OGCB:DORS *DRP:RIV *TECH ED. *SC:DRP:RIV *D:DRP:RIVN.ME PCWen/vsb MASatorius MFMejac WDJohnson ABBeachDATE 06/01/93 06/02/93 06/02/93 06/04/93 06/04/93*PM:PDV:NRR l *C:SPLB:DSSA:NRR *D:DSSA:NRR C:OGCB:DORS:NRR DLEKokaiko CEMcCracken l ACThadani GHMarcus( r lines06/08/93 1 06/09/93 06/10/93 06//6/93 06/,z/93DOCUMENT NAME: INTDAFWP.WP 6 IN 93-xxJune xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Mark A. Satorius, RIV(817) 860-8141William D. Johnson, RIV(817) 860-8148Peter C. Wen, NRR(301) 504-2832Attachments:1. Figure 1, Existing South Texas Project TDAFWP Steam Supply and ExhaustSystem2. Figure 2, Modified South Texas Project TDAFWP Steam Supply and ExhaustSystem3. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB:DORS *DRP:RIV *TECH ED. *SC:DRP:RIV *D:DRP:RIVNAME PCWen/vsb MASatorius MFMejac WDJohnson ABBeachDATE 06/01/93 06/02/93 06/02/93 06/04/93 06/04/93PM PDV:NRR P e E BC:OGCB:DORS:NRR D:DORS:NRRLEKokaiko CEMcCI J dThadani GHMarcus BKGrimes06/1 /93 06/ "/93 06/f/L93 06/ /93 06/ /93DOCUMENT NAME: INTDAFWP.WPl
D:DORS:NRR


06-S12-1119 14t130..106/04/93 15:05;301 5 34 37R I'J US NRC FTS 728-327'3NRC WHZTEl LINT F002P.02IN 93-xxJunt Xx, 1993 rhis iofwmtion notice requires no specific act on or written response. Ifyew ton & questions about the information in his notice, please contact*a of tochnical contacts listed bolow or th appropriate Office ofbtlw lector Regulation (NRR) project managerToc"ial contatts:Brian K. Gripes, DirectorDivision of OPerating Reactor SupportOffice of Nuclear Reactor RegulationMKrk A. Satorius, RI'(817) 660-4141William D. Johnton, RIV(817) B6O-814BPeter C. Win NRR(301) 504-28i2fttocwtsz:11. fig" It Existing South Texas Project TDAfWP Steam Supply9 t1. FlKrp 2, Modified South Texas Project TDA4I P Steam SupplyS. stoe.ist tf Recently Issued NRC Information Noice~sand Exhaustand ExhaustIQ2I fIaCURR E _.__ I___-(, 0 1 93PCmn/sb tSu:D~ohnn-/0ul __ 06/02/931 0/P3 OS .6 / .CttKn-ANtrRRD OSZiARR9C OCt!R!OOR$:tRRDe:nRS!NRR-------- -IACHhadani Marcus bKoritmeU- a 0r:w : 1"TuAokIrP
CEMcCracken


IN 93-xxJune xx, 1993Page 3 ofThis information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Mark A. Satorius, RIV(817) 860-8141William D. Johnson, RIV(817) 860-8148Peter C. Wen, NRR(301) 504-2832Attachment:List of Recently Issued NRC Information Notices_. __IOFFICE OGCB:DORS DRP:RIV TECH ED. SC:DRP:RIV D:DRP:RIVNAME PCWen/vsb MASatorius A. WDJohnson ABBeachDATE .06/ I /93 _ 06/ /93 06/-L193 f06/ /93 l 06/ /93....BC:SPLB:DSSA:NRRD:DSSA:NRRBC:OGCB:DORS:NRRD:DORS:NRRCEMcCracken ACThadani GHMarcus BKGrimes06/ /93 06/ /93 06/ /93 06/ /93UMUWMMI NAMt: IN IUDAWFW. WF
ACThadani


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GHMarcus BKGrimes 06/ /93 06/ /93 06/ /93 06/ /93 UMUWMMI NAMt: IN IUDAWFW. WF}}


{{Information notice-Nav}}
{{Information notice-Nav}}

Revision as of 13:54, 31 August 2018

Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps
ML031070374
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, 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
Issue date: 07/09/1993
From: Grimes B K
Office of Nuclear Reactor Regulation
To:
References
IN-93-051, NUDOCS 9307010233
Download: ML031070374 (12)
v • d • e


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

  • NRC Information

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

Loss of Control Room Annunciators

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
  • D: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

  • C:SPLB:DSSA:NRR
  • D:DSSA:NRR
  • C:OGCB:DORS: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
  • D: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

  • D: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
  • D: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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