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

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| issue date = 07/09/1993
| issue date = 07/09/1993
| title = Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps
| title = Repetitive Overspeed Tripping of Turbine-Driven Auxiliary Feedwater Pumps
| author name = Grimes B K
| author name = Grimes B
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
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| page count = 12
| page count = 12
}}
}}
{{#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.
nuclear power
 
All holders of operating licenses or construction permits for
 
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.
information
 
The U.S. Nuclear Regulatory Commission (NRC) is issuing this               of turbine- notice to alert addressees to the problem of repetitive       tripping
 
Project  Electric
 
driven auxiliary feedwater pumps (TDAFWPs) at the South Texas           the
 
Generating Station. It is expected that recipients will         review
 
actions, as
 
information for applicability to their facilities and consider contained in
 
appropriate, to avoid similar problems. However, suggestions no specific
 
this information notice are not NRC requirements; therefore, action or written response is required.


==Description of Circumstances==
==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 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
On December 27, 1992, Houston Lighting & Power Company (the licensee)         receiving a
 
performed a monthly surveillance test on its Unit 1 TDAFWP. After                 The
 
start signal, the pump immediately tripped on an     overspeed   condition.
 
local  manual
 
operators repeated the surveillance test after a successful the licensee
 
start. On this attempt the pump successfully started, and
 
subsequently considered the pump operable.
 
water level
 
On January 23, 1993, Unit 2 tripped from 100-percent power on low
 
in one of the steam generators. The trip     occurred because   electro-hydraulic
 
was lost. The
 
control oil to the steam generator main feedwater pump turbine       longer  required.
 
secured  when  no
 
Unit 2 TDAFWP started on demand and was later                       attempted    to
 
After the pump was secured, problems occurred     when operators
 
from  the  control  room.    (See
 
relatch MOV-514 (the TDAFWP trip/throttle valve)                               a
 
The  licensee  conducted
 
Figure 1.) The pump was declared inoperable.                           to resolve the
 
significant amount of troubleshooting and testing on the TDAFWP was identified
 
MOV-514 relatch problem and another speed   control problem   that
 
was completed
 
during the testing. After the operability surveillance test was restarted on
 
successfully, the TDAFWP was declared   operable and the unit
 
January 25, 1993.
 
a routine monthly
 
On January 28, 1993, the Unit 1 TDAFWP was tested as part of
 
immediately  tripped    on  an overspeed
 
surveillance. When started, the TDAFWP                                   28 through
 
condition and was subsequently declared   inoperable.   From January
 
9307010233        P                       PC     w3         9t - oSI                 915 I
 
-I
 
IN 93-51 July 9, 1993 and
 
January 30, 1993, the licensee undertook an extensive testing with          the TDAFWP.
 
troubleshooting effort to determine  the cause  of the  problem
 
Several  problems  (overspeed      tripping, Numerous pump starts were completed.                                            full- and inability  to  maintain      rated
 
lack of speed control, oscillations,                                      the Unit 1 load, steady-state speed) were identified. On January 30, 1993,                      and
 
TDAFWP was declared operable following extensive maintenance activities
 
the successful completion of the surveillance test.
 
direction of
 
On February 1, 1993, the Unit 1 TDAFWP was tested again at the considering the
 
the Unit 1 operations manager in order to ensure operability,                signal, the
 
numerous problems encountered previously. After receiving a start
 
pump tripped on an overspeed condition and was declared inoperable.
 
Two steam- On February 3, 1993, Unit 2 was operating at 100-percent power.                  feedwater
 
driven steam generator main feedwater pumps and one electric        startup
 
feedwater
 
pump were providing feed flow to the steam generators. The startup        being
 
pump tripped when the pump lubricating oil duplex strainers were                  to avoid
 
shifted. Operators began to manually ramp down power but were          unable
 
initiated      a  manual
 
the low steam generator level. The operators subsequently            system    trip
 
reactor trip before receiving an automatic reactor protection                  Unit 2 signal on low steam generator level. Following the plant trip, the
 
the  steam    generators.
 
TDAFWP received an automatic signal to supply water to
 
The pump started but immediately tripped on an overspeed condition.
 
in the
 
On February 4, 1993, Unit 1 commenced a shutdown to place the reactor      had  not  been
 
mode required by the Technical Specifications because    the  TDAFWP
 
allowed      by  the
 
restored to an operable condition within the outage time
 
Technical Specifications.
 
NRC
 
Further details can be found in License Event Report 50-498/93-007 and
 
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          of
 
overspeed trips, the proximate cause was determined to be the intrusion
 
water into the TDAFWP turbine that adversely  affected  its  performance.
 
tests
 
However, this cause was effectively masked for several surveillance
 
because the surveillance test program established  to  satisfy    the    operability
 
to
 
requirements of the Technical Specifications was not sufficiently rigorous  conditions.
 
assure that the testing was performed under  suitable  environmental
 
of the
 
The TDAFWP was not returned to its normal standby condition before each
 
TDAFWP surveillance tests performed on December  27,  1992,    and
 
normal
 
January 30, 1993. Because of this, the pump was not tested in its                not
 
standby condition and degraded conditions  affecting  operability      were
 
revealed.
 
IN 93-51 July 9, 1993 Unit 2 The licensee determined that the root cause of the February 3, 1993,with an
 
TDAFWP overspeed trip was an incorrect  valve lineup  in conjunction
 
located
 
Inoperable or degraded steam trap. The valves and the steam trap are TDAFWP
 
admission line.  (See Figure  1.)    The
 
in the drain line from the steam                                              supply
 
overspeed trip was caused by excessive condensate buildup in the steam
 
(MOV-514  in Figure  1).  The  excessive
 
line upstream of the trip/throttle valve                                        was
 
condensate had accumulated because the steam trap bypass valve, MS-517,        an
 
the steam trap  had degraded    to  such
 
incorrectly positioned (closed) and                                      condenser.
 
extent that it was no longer capable  of passing  condensate  to  the
 
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.
 
HPCI,
*    IE Information Notice 86-14, Supplement 1, "Overspeed Trips of AFW,
      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 If
 
This information notice requires no specific action or written response.
 
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                                                                PIPE CAP WITH ORIFICE
 
LINE DRAIN                                                                If  (UNIT I ONLY)
          VALVES
 
MS
 
371 MS
 
370                          MS TURBINE CASING
 
FO 7537B              373 DRAIN VALVE
 
~1 II
 
STEAM TRAP              STEAM          FO 7537A--
      BYPASS
 
VALVE
 
TRAP
 
Yl                                              (D% %Dn
 
w  I1
                                                                                                      °% I'-
                                                                                      CONDENSER        I-a%0 w r
 
0D
 
FIGURE 1 TDAFWP STEAM SUPPLY AND    EXHAUST SYSTEM (UNMODIFIED)
 
MOV-143 STEAM EXHAUST
 
LINE
 
===STEAM ADMISSION===
      LINE
 
MOV-514 TERRY
 
TURBINE                                        C
 
STEAM ADMISSION


-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.
UNE DRAIN


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.
VALVES


* .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
MS


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)
370                      MS TURBINE CASING
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
FO 7537B          373 DRAIN VALVE


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
MS


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
515 STEAM TRAP            SPOOL


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
BYPASS              PIECE                                                          m'z    ~  --
        VALVE


}}
MS                                                                " MD3%Dt
 
HAQ
 
516                                                                  %O D
 
CONDENSER  " D
 
Wa  "
                                          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          Extended Storage of            07/08/93  All licensees authorized
 
Sealed Sources                            to possess sealed sources.
 
93-49          Improper Integration of        07/08/93  All holders of OLs or CPs
 
Software into Operating                  for nuclear power reactors.
 
Practices
 
93-48          Failure of Turbine-            7/6/93    All holders of OLs or CPs
 
Driven Main Feedwater                    for nuclear power reactors.
 
Pump to Trip Because of
 
Contaminated Oil
 
92-06,        Reliability of ATWS            07/01/93  All holders of OLs or CPs
 
Supp. 1        Mitigation Systems and                    for nuclear power reactors.
 
Other NRC-Required Equip- ment not Controlled by
 
Plant Technical Specifica- tion
 
93-47          Unrecognized Loss of          06/18/93  All holders of OLs or CPs
 
Control Room Annunciators                for nuclear power reactors.
 
93-46          Potential Problem with        6/10/93    All holders of OLs or CPs
 
Westinghouse Rod Control                  for Westinghouse (W)-
              System and Inadvertent                    designed nuclear power
 
Withdrawal of A Single                    reactors.
 
Rod Control Cluster Assembly
 
93-45          Degradation of Shutdown      06/16/93    All holders of OLs or CPs
 
Cooling System Performance                for nuclear power reactors.
 
93-44          Operational Challenges        06/15/93    All holders of OLs or CPs
 
During A Dual-Unit                        for nuclear power reactors.
 
Transient
 
93-43          Use of Inappropriate          06/10/93    All holders of OLs or CPs
 
Lubrication Oils in                      for nuclear power reactors.
 
Safety-Related Applications
 
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 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
 
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 l
 
PM PDV:NRR
 
LEKokaiko
 
06/1 /93 P
 
CEMcCI
 
e
 
J      E
 
dThadani
 
BC:OGCB:DORS:NRR
 
GHMarcus
 
D:DORS:NRR
 
BKGrimes
 
06/ "/93          06/f/L93    06/  /93            06/  /93 DOCUMENT NAME:    INTDAFWP.WP
 
06/04/93        15:05            R I'J US NRC FTS 728-327'3
                                                                                                    002
  06-S12-1119    14t130      ;301
                                5 34        37              NRC WHZTEl LINT F
 
.        .1                                                                                          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
 
Brian K. Gripes, Director
 
Division of OPerating Reactor Support
 
Office of Nuclear Reactor Regulation
 
Toc"ial contatts:            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 and Exhaust
 
9    t
 
1.      FlKrp    2, Modified South Texas Project TDA4I P Steam Supply and Exhaust
 
S.stoe
 
.      ist tf Recently Issued NRC Information Noice~s
 
I              Q2I  fIaCURR        E            _.__          I___
                                    -(,                  0    1 93 PCmn/sb                tSu:D~ohnn
 
-/0ul              __
                                        OS              06/02/931      0/P3                /  .6.
 
CttKn-ANtrRR                D OSZiARR    9C OCt!R!OOR$:tRR          De:nRS!NRR
 
-                -------            -I
 
ACHhadani      Marcus                    bKoritme
 
U-    0r            a
 
: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}}


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

Latest revision as of 04:21, 24 November 2019

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
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

nuclear power

All holders of operating licenses or construction permits for

reactors.

Purpose

information

The U.S. Nuclear Regulatory Commission (NRC) is issuing this of turbine- notice to alert addressees to the problem of repetitive tripping

Project Electric

driven auxiliary feedwater pumps (TDAFWPs) at the South Texas the

Generating Station. It is expected that recipients will review

actions, as

information for applicability to their facilities and consider contained in

appropriate, to avoid similar problems. However, suggestions no specific

this information notice are not NRC requirements; therefore, action or written response is required.

Description of Circumstances

On December 27, 1992, Houston Lighting & Power Company (the licensee) receiving a

performed a monthly surveillance test on its Unit 1 TDAFWP. After The

start signal, the pump immediately tripped on an overspeed condition.

local manual

operators repeated the surveillance test after a successful the licensee

start. On this attempt the pump successfully started, and

subsequently considered the pump operable.

water level

On January 23, 1993, Unit 2 tripped from 100-percent power on low

in one of the steam generators. The trip occurred because electro-hydraulic

was lost. The

control oil to the steam generator main feedwater pump turbine longer required.

secured when no

Unit 2 TDAFWP started on demand and was later attempted to

After the pump was secured, problems occurred when operators

from the control room. (See

relatch MOV-514 (the TDAFWP trip/throttle valve) a

The licensee conducted

Figure 1.) The pump was declared inoperable. to resolve the

significant amount of troubleshooting and testing on the TDAFWP was identified

MOV-514 relatch problem and another speed control problem that

was completed

during the testing. After the operability surveillance test was restarted on

successfully, the TDAFWP was declared operable and the unit

January 25, 1993.

a routine monthly

On January 28, 1993, the Unit 1 TDAFWP was tested as part of

immediately tripped on an overspeed

surveillance. When started, the TDAFWP 28 through

condition and was subsequently declared inoperable. From January

9307010233 P PC w3 9t - oSI 915 I

-I

IN 93-51 July 9, 1993 and

January 30, 1993, the licensee undertook an extensive testing with the TDAFWP.

troubleshooting effort to determine the cause of the problem

Several problems (overspeed tripping, Numerous pump starts were completed. full- and inability to maintain rated

lack of speed control, oscillations, the Unit 1 load, steady-state speed) were identified. On January 30, 1993, and

TDAFWP was declared operable following extensive maintenance activities

the successful completion of the surveillance test.

direction of

On February 1, 1993, the Unit 1 TDAFWP was tested again at the considering the

the Unit 1 operations manager in order to ensure operability, signal, the

numerous problems encountered previously. After receiving a start

pump tripped on an overspeed condition and was declared inoperable.

Two steam- On February 3, 1993, Unit 2 was operating at 100-percent power. feedwater

driven steam generator main feedwater pumps and one electric startup

feedwater

pump were providing feed flow to the steam generators. The startup being

pump tripped when the pump lubricating oil duplex strainers were to avoid

shifted. Operators began to manually ramp down power but were unable

initiated a manual

the low steam generator level. The operators subsequently system trip

reactor trip before receiving an automatic reactor protection Unit 2 signal on low steam generator level. Following the plant trip, the

the steam generators.

TDAFWP received an automatic signal to supply water to

The pump started but immediately tripped on an overspeed condition.

in the

On February 4, 1993, Unit 1 commenced a shutdown to place the reactor had not been

mode required by the Technical Specifications because the TDAFWP

allowed by the

restored to an operable condition within the outage time

Technical Specifications.

NRC

Further details can be found in License Event Report 50-498/93-007 and

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 of

overspeed trips, the proximate cause was determined to be the intrusion

water into the TDAFWP turbine that adversely affected its performance.

tests

However, this cause was effectively masked for several surveillance

because the surveillance test program established to satisfy the operability

to

requirements of the Technical Specifications was not sufficiently rigorous conditions.

assure that the testing was performed under suitable environmental

of the

The TDAFWP was not returned to its normal standby condition before each

TDAFWP surveillance tests performed on December 27, 1992, and

normal

January 30, 1993. Because of this, the pump was not tested in its not

standby condition and degraded conditions affecting operability were

revealed.

IN 93-51 July 9, 1993 Unit 2 The licensee determined that the root cause of the February 3, 1993,with an

TDAFWP overspeed trip was an incorrect valve lineup in conjunction

located

Inoperable or degraded steam trap. The valves and the steam trap are TDAFWP

admission line. (See Figure 1.) The

in the drain line from the steam supply

overspeed trip was caused by excessive condensate buildup in the steam

(MOV-514 in Figure 1). The excessive

line upstream of the trip/throttle valve was

condensate had accumulated because the steam trap bypass valve, MS-517, an

the steam trap had degraded to such

incorrectly positioned (closed) and condenser.

extent that it was no longer capable of passing condensate to the

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

HPCI, and RCIC Turbines," dated August 26, 1991.

Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type

Governors," dated March 18, 1988.

HPCI,

and RCIC Turbines," dated December 17, 1986.

Control Problems," dated March 10, 1986.

.IN

  • 93-51 July 9, 1993 If

This information notice requires no specific action or written response.

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 PIPE CAP WITH ORIFICE

LINE DRAIN If (UNIT I ONLY)

VALVES

MS

371 MS

370 MS TURBINE CASING

FO 7537B 373 DRAIN VALVE

~1 II

STEAM TRAP STEAM FO 7537A--

BYPASS

VALVE

TRAP

Yl (D% %Dn

w I1

°% I'-

CONDENSER I-a%0 w r

0D

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 MS TURBINE CASING

FO 7537B 373 DRAIN VALVE

MS

515 STEAM TRAP SPOOL

BYPASS PIECE m'z ~ --

VALVE

MS " MD3%Dt

HAQ

516 %O D

CONDENSER " D

Wa "

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 Extended Storage of 07/08/93 All licensees authorized

Sealed Sources to possess sealed sources.

93-49 Improper Integration of 07/08/93 All holders of OLs or CPs

Software into Operating for nuclear power reactors.

Practices

93-48 Failure of Turbine- 7/6/93 All holders of OLs or CPs

Driven Main Feedwater for nuclear power reactors.

Pump to Trip Because of

Contaminated Oil

92-06, Reliability of ATWS 07/01/93 All holders of OLs or CPs

Supp. 1 Mitigation Systems and for nuclear power reactors.

Other NRC-Required Equip- ment not Controlled by

Plant Technical Specifica- tion

93-47 Unrecognized Loss of 06/18/93 All holders of OLs or CPs

Control Room Annunciators for nuclear power reactors.

93-46 Potential Problem with 6/10/93 All holders of OLs or CPs

Westinghouse Rod Control for Westinghouse (W)-

System and Inadvertent designed nuclear power

Withdrawal of A Single reactors.

Rod Control Cluster Assembly

93-45 Degradation of Shutdown 06/16/93 All holders of OLs or CPs

Cooling System Performance for nuclear power reactors.

93-44 Operational Challenges 06/15/93 All holders of OLs or CPs

During A Dual-Unit for nuclear power reactors.

Transient

93-43 Use of Inappropriate 06/10/93 All holders of OLs or CPs

Lubrication Oils in for nuclear power reactors.

Safety-Related Applications

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 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

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 l

PM PDV:NRR

LEKokaiko

06/1 /93 P

CEMcCI

e

J E

dThadani

BC:OGCB:DORS:NRR

GHMarcus

D:DORS:NRR

BKGrimes

06/ "/93 06/f/L93 06/ /93 06/ /93 DOCUMENT NAME: INTDAFWP.WP

06/04/93 15:05 R I'J US NRC FTS 728-327'3

002

06-S12-1119 14t130 ;301

5 34 37 NRC WHZTEl LINT F

. .1 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

Brian K. Gripes, Director

Division of OPerating Reactor Support

Office of Nuclear Reactor Regulation

Toc"ial contatts: 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 and Exhaust

9 t

1. FlKrp 2, Modified South Texas Project TDA4I P Steam Supply and Exhaust

S.stoe

. ist tf Recently Issued NRC Information Noice~s

I Q2I fIaCURR E _.__ I___

-(, 0 1 93 PCmn/sb tSu:D~ohnn

-/0ul __

OS 06/02/931 0/P3 / .6.

CttKn-ANtrRR D OSZiARR 9C OCt!R!OOR$:tRR De:nRS!NRR

- ------- -I

ACHhadani Marcus bKoritme

U- 0r a

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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