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

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{{#Wiki_filter:r -UNITED STATES NUCLEAR REGULATORY
{{#Wiki_filter:r   -
                                      UNITED STATES


COMMISSION
NUCLEAR REGULATORY COMMISSION


===OFFICE OF NUCLEAR REACTOR REGULATION===
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 9, 1993 NRC INFORMATION


NOTICE 93-51: REPETITIVE
WASHINGTON, D.C. 20555 July 9, 1993 NRC INFORMATION NOTICE 93-51:     REPETITIVE OVERSPEED TRIPPING OF TURBINE-DRIVEN


OVERSPEED
AUXILIARY FEEDWATER PUMPS


TRIPPING OF TURBINE-DRIVEN
==Addressees==
nuclear power
 
All holders of operating licenses or construction permits for


AUXILIARY
reactors.


FEEDWATER
==Purpose==
information


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


==Addressees==
Project  Electric
All holders of operating


licenses or construction
driven auxiliary feedwater pumps (TDAFWPs) at the South Texas            the


permits for nuclear power reactors.
Generating Station. It is expected that recipients will        review


==Purpose==
actions, as
The U.S. Nuclear Regulatory


Commission (NRC) is issuing this information
information for applicability to their facilities and consider contained in


notice to alert addressees
appropriate, to avoid similar problems. However, suggestions no specific


to the problem of repetitive
this information notice are not NRC requirements; therefore, action or written response is required.


tripping of turbine-driven auxiliary
==Description of Circumstances==
On December 27, 1992, Houston Lighting & Power Company (the licensee)        receiving a


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


pumps (TDAFWPs)
start signal, the pump immediately tripped on an    overspeed    condition.
at the South Texas Project Electric Generating


Station. It is expected that recipients
local  manual


will review the information
operators repeated the surveillance test after a successful the licensee


for applicability
start. On this attempt the pump successfully started, and


to their facilities
subsequently considered the pump operable.


and consider actions, as appropriate, to avoid similar problems.
water level


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


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


in this information
was lost. The


notice are not NRC requirements;
control oil to the steam generator main feedwater pump turbine        longer  required.
therefore, no specific action or written response is required.Description


of Circumstances
secured  when  no


On December 27, 1992, Houston Lighting & Power Company (the licensee)performed
Unit 2 TDAFWP started on demand and was later                        attempted    to


a monthly surveillance
After the pump was secured, problems occurred    when  operators


test on its Unit 1 TDAFWP. After receiving
from  the  control  room.     (See


a start signal, the pump immediately
relatch MOV-514 (the TDAFWP trip/throttle valve)                                a


tripped on an overspeed
The  licensee  conducted


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


The operators
significant amount of troubleshooting and testing on the TDAFWP was identified


repeated the surveillance
MOV-514 relatch problem and another speed    control  problem  that


test after a successful
was completed


local manual start. On this attempt the pump successfully
during the testing. After the operability surveillance test was restarted on


started, and the licensee subsequently
successfully, the TDAFWP was declared  operable and the unit


considered
January 25, 1993.


the pump operable.On January 23, 1993, Unit 2 tripped from 100-percent
a routine monthly


power on low water level in one of the steam generators.
On January 28, 1993, the Unit 1 TDAFWP was tested as part of


The trip occurred because electro-hydraulic
immediately  tripped    on  an overspeed


control oil to the steam generator
surveillance. When started, the TDAFWP                                    28 through


main feedwater
condition and was subsequently declared  inoperable.    From  January


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
9307010233        P                      PC      w3          9t - oSI                915 I


attempted
-I


to relatch MOV-514 (the TDAFWP trip/throttle
IN 93-51 July 9, 1993 and


valve) from the control room. (See Figure 1.) The pump was declared inoperable.
January 30, 1993, the licensee undertook an extensive testing with          the TDAFWP.


The licensee conducted
troubleshooting effort to determine  the cause  of the  problem


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


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


and testing on the TDAFWP to resolve the MOV-514 relatch problem and another speed control problem that was identified
TDAFWP was declared operable following extensive maintenance activities


during the testing. After the operability
the successful completion of the surveillance test.


surveillance
direction of


test was completed successfully, the TDAFWP was declared operable and the unit was restarted
On February 1, 1993, the Unit 1 TDAFWP was tested again at the considering the


on January 25, 1993.On January 28, 1993, the Unit 1 TDAFWP was tested as part of a routine monthly surveillance.
the Unit 1 operations manager in order to ensure operability,                 signal, the


When started, the TDAFWP immediately
numerous problems encountered previously. After receiving a start


tripped on an overspeed condition
pump tripped on an overspeed condition and was declared inoperable.


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


declared inoperable.
driven steam generator main feedwater pumps and one electric        startup


From January 28 through 9307010233 P 9t PC w3 -oSI 9 15 I
feedwater


-I IN 93-51 July 9, 1993 January 30, 1993, the licensee undertook
pump were providing feed flow to the steam generators. The startup        being


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


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


effort to determine
initiated      a  manual


the cause of the problem with the TDAFWP.Numerous pump starts were completed.
the low steam generator level. The operators subsequently            system    trip


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


tripping, lack of speed control, oscillations, and inability
the  steam    generators.


to maintain rated full-load, steady-state
TDAFWP received an automatic signal to supply water to


speed) were identified.
The pump started but immediately tripped on an overspeed condition.


On January 30, 1993, the Unit 1 TDAFWP was declared operable following
in the


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


maintenance
mode required by the Technical Specifications because    the  TDAFWP


activities
allowed      by  the


and the successful
restored to an operable condition within the outage time


completion
Technical Specifications.


of the surveillance
NRC


test.On February 1, 1993, the Unit 1 TDAFWP was tested again at the direction
Further details can be found in License Event Report 50-498/93-007 and


of the Unit 1 operations
Inspection Reports 50-498; 50-499/93-05 and 50-498; 50-499/93-07.


manager in order to ensure operability, considering
Discussion


the numerous problems encountered
Although the licensee did not identify the root cause of the Unit 1 TDAFWP          of


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


After receiving
water into the TDAFWP turbine that adversely  affected  its  performance.


a start signal, the pump tripped on an overspeed
tests


condition
However, this cause was effectively masked for several surveillance


and was declared inoperable.
because the surveillance test program established  to  satisfy    the    operability


On February 3, 1993, Unit 2 was operating
to


at 100-percent
requirements of the Technical Specifications was not sufficiently rigorous  conditions.


power. Two steam-driven steam generator
assure that the testing was performed under  suitable  environmental


main feedwater
of the


pumps and one electric startup feedwater pump were providing
The TDAFWP was not returned to its normal standby condition before each


feed flow to the steam generators.
TDAFWP surveillance tests performed on December  27,  1992,    and


The startup feedwater pump tripped when the pump lubricating
normal


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


were being shifted. Operators
standby condition and degraded conditions  affecting  operability      were


began to manually ramp down power but were unable to avoid the low steam generator
revealed.


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


subsequently
TDAFWP overspeed trip was an incorrect  valve lineup  in conjunction


initiated
located


a manual reactor trip before receiving
Inoperable or degraded steam trap. The valves and the steam trap are TDAFWP


an automatic
admission line.  (See Figure  1.)    The


reactor protection
in the drain line from the steam                                              supply


system trip signal on low steam generator
overspeed trip was caused by excessive condensate buildup in the steam


level. Following
(MOV-514  in Figure  1).   The  excessive


the plant trip, the Unit 2 TDAFWP received an automatic
line upstream of the trip/throttle valve                                        was


signal to supply water to the steam generators.
condensate had accumulated because the steam trap bypass valve, MS-517,        an


The pump started but immediately
the steam trap  had degraded    to  such


tripped on an overspeed
incorrectly positioned (closed) and                                      condenser.


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


On February 4, 1993, Unit 1 commenced
The licensee took the following corrective actions related to the hardware


a shutdown to place the reactor in the mode required by the Technical
modifications for both units:
*    The trip/throttle valves and governors were sent to the respective


Specifications
vendors for complete refurbishment and testing. The gearing arrangement


because the TDAFWP had not been restored to an operable condition
of the trip/throttle valve was modified to ensure slower stroke time, thus enabling a more positive governor response.


within the outage time allowed by the Technical
*    The TDAFWP drain system was modified to remove the steam traps in the


Specifications.
steamline drain system, replacing them with a spool piece. Also, the


Further details can be found in License Event Report 50-498/93-007 and NRC Inspection
trip/throttle valve high-pressure steam leakoff was separated from the


Reports 50-498; 50-499/93-05 and 50-498; 50-499/93-07.
turbine casing drain line and rerouted to the sump to prevent possible


Discussion
intrusion of steam into the turbine casing. (See Figure 2.)
Related Generic Communications


Although the licensee did not identify the root cause of the Unit 1 TDAFWP overspeed
*    NRC Information Notice 86-14, Supplement 2, "Overspeed Trips of AFW,
      HPCI, and RCIC Turbines," dated August 26, 1991.


trips, the proximate
*    NRC Information Notice 88-09, "Reduced Reliability of Steam-Driven


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


to be the intrusion
Governors," dated March 18, 1988.


of water into the TDAFWP turbine that adversely
HPCI,
*    IE Information Notice 86-14, Supplement 1, "Overspeed Trips of AFW,
      and RCIC Turbines," dated December 17, 1986.


affected its performance.
*    IE Information Notice 86-14, "PWR Auxiliary Feedwater Pump Turbine


However, this cause was effectively
Control Problems," dated March 10, 1986.


masked for several surveillance
.IN


tests because the surveillance
*            93-51 July 9, 1993 If


test program established
This information notice requires no specific action or written response.


to satisfy the operability
you have any questions about  the information in this notice,  please  contact


requirements
one of the technical contacts listed below or the appropriate Office of


of the Technical
Nuclear Reactor Regulation (NRR) project manager.


Specifications
Brian K. Grimes, Director


was not sufficiently
Division of Operating Reactor Support


rigorous to assure that the testing was performed
Office of Nuclear Reactor Regulation


under suitable environmental
Technical contacts:  Mark A. Satorius, RIV


conditions.
(817) 860-8141 William D. Johnson, RIV


The TDAFWP was not returned to its normal standby condition
(817) 860-8148 Peter C. Wen, NRR


before each of the TDAFWP surveillance
(301) 504-2832 Attachments:
1. Figure 1, Existing South Texas Project


tests performed
TDAFWP Steam Supply and Exhaust System


on December 27, 1992, and January 30, 1993. Because of this, the pump was not tested in its normal standby condition
2. Figure 2, Modified South Texas Project


and degraded conditions
TDAFWP Steam Supply and Exhaust System


affecting
3. List of Recently Issued NRC Information Notices


operability
MOV-143 STEAM EXHAUST


were not revealed.
LINE


IN 93-51 July 9, 1993 The licensee determined
===STEAM ADMISSION===
      LINE


that the root cause of the February 3, 1993, Unit 2 TDAFWP overspeed
MOV-514 TERRY


trip was an incorrect
TURBINE                                              (
    STEAM ADMISSION                                                                PIPE CAP WITH ORIFICE


valve lineup in conjunction
LINE DRAIN                                                                If  (UNIT I ONLY)
          VALVES


with an Inoperable
MS


or degraded steam trap. The valves and the steam trap are located in the drain line from the steam admission
371 MS


line. (See Figure 1.) The TDAFWP overspeed
370                          MS TURBINE CASING


trip was caused by excessive
FO 7537B              373 DRAIN VALVE


condensate
~1 II


buildup in the steam supply line upstream of the trip/throttle
STEAM TRAP              STEAM          FO 7537A--
      BYPASS


valve (MOV-514 in Figure 1). The excessive condensate
VALVE


had accumulated
TRAP


because the steam trap bypass valve, MS-517, was incorrectly
Yl                                              (D% %Dn


positioned (closed) and the steam trap had degraded to such an extent that it was no longer capable of passing condensate
w  I1
                                                                                                      °% I'-
                                                                                      CONDENSER        I-a%0 w r


to the condenser.
0D


The licensee took the following
FIGURE 1 TDAFWP STEAM SUPPLY AND    EXHAUST SYSTEM (UNMODIFIED)


corrective
MOV-143 STEAM EXHAUST


actions related to the hardware modifications
LINE


for both units:* The trip/throttle
===STEAM ADMISSION===
      LINE


valves and governors
MOV-514 TERRY


were sent to the respective
TURBINE                                        C


vendors for complete refurbishment
STEAM ADMISSION


and testing. The gearing arrangement
UNE DRAIN


of the trip/throttle
VALVES


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
MS


drain system, replacing
370                      MS TURBINE CASING


them with a spool piece. Also, the trip/throttle
FO 7537B          373 DRAIN VALVE


valve high-pressure
MS


steam leakoff was separated
515 STEAM TRAP            SPOOL


from the turbine casing drain line and rerouted to the sump to prevent possible intrusion
BYPASS              PIECE                                                          m'z    ~  --
        VALVE


of steam into the turbine casing. (See Figure 2.)Related Generic Communications
MS                                                                " MD3%Dt


* NRC Information
HAQ


Notice 86-14, Supplement
516                                                                  %O D


2, "Overspeed
CONDENSER  " D


Trips of AFW, HPCI, and RCIC Turbines," dated August 26, 1991.* NRC Information
Wa  "
                                          FIGURE 2 TDAFWP STEAM SUPPLY AND EXHAUST SYSTEM (MODIFED)


Notice 88-09, "Reduced Reliability
Attachment 3 IN 93-51 July 9, 1993 LIST OF RECENTLY ISSUED


of Steam-Driven
NRC INFORMATION NOTICES


Auxiliary
Information                                  Date of


Feedwater
Notice No.            Subject                Issuance  Issued to


Pumps Caused by Instability
93-50          Extended Storage of            07/08/93  All licensees authorized


of Woodward PG-PL Type Governors," dated March 18, 1988.* IE Information
Sealed Sources                            to possess sealed sources.


Notice 86-14, Supplement
93-49          Improper Integration of        07/08/93  All holders of OLs or CPs


1, "Overspeed
Software into Operating                  for nuclear power reactors.


Trips of AFW, HPCI, and RCIC Turbines," dated December 17, 1986.* IE Information
Practices


Notice 86-14, "PWR Auxiliary
93-48          Failure of Turbine-            7/6/93    All holders of OLs or CPs


Feedwater
Driven Main Feedwater                     for nuclear power reactors.


Pump Turbine Control Problems," dated March 10, 1986.
Pump to Trip Because of


* .IN 93-51 July 9, 1993 This information
Contaminated Oil


notice requires no specific action or written response.
92-06,        Reliability of ATWS            07/01/93  All holders of OLs or CPs


If you have any questions
Supp. 1        Mitigation Systems and                    for nuclear power reactors.


about the information
Other NRC-Required Equip- ment not Controlled by


in this notice, please contact one of the technical
Plant Technical Specifica- tion


contacts listed below or the appropriate
93-47          Unrecognized Loss of          06/18/93  All holders of OLs or CPs


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Control Room Annunciators                for nuclear power reactors.


===Reactor Support Office of Nuclear Reactor Regulation===
93-46          Potential Problem with        6/10/93    All holders of OLs or CPs
Technical


contacts:
Westinghouse Rod Control                  for Westinghouse (W)-
Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachments:
              System and Inadvertent                    designed nuclear power
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
Withdrawal of A Single                    reactors.


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)
Rod Control Cluster Assembly
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
93-45          Degradation of Shutdown      06/16/93    All holders of OLs or CPs


NOTICES Information
Cooling System Performance                for nuclear power reactors.


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


of Software into Operating Practices Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated
During A Dual-Unit                        for nuclear power reactors.


Oil Reliability
Transient


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


Systems and Other NRC-Required
Lubrication Oils in                      for nuclear power reactors.


Equip-ment not Controlled
Safety-Related Applications


by Plant Technical
OL = Operating License


Specifica- tion Unrecognized
CP - Construction Permit


===Loss of Control Room Annunciators===
\,-
Potential
                                                                  IN 93-51 July 9, 1993 This information notice requires no specific action or written response. If


Problem with Westinghouse
you have any questions about the information in this notice, please contact


===Rod Control System and Inadvertent===
one of the technical contacts listed below or the appropriate Office of
Withdrawal


of A Single Rod Control Cluster Assembly Degradation
Nuclear Reactor Regulation (NRR) project manager.


of Shutdown Cooling System Performance
orig /s/'d by BKGrimes


Operational
Brian K. Grimes, Director


Challenges
Division of Operating Reactor Support


During A Dual-Unit Transient Use of Inappropriate
Office of Nuclear Reactor Regulation


Lubrication
Technical contacts:    Mark A. Satorius, RIV


Oils in Safety-Related
(817) 860-8141 William D. Johnson, RIV


===Applications===
(817) 860-8148 Peter C. Wen, NRR
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
(301) 504-2832 Attachments:
1. Figure 1, Existing South Texas Project TDAFWP


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
Steam Supply and Exhaust System


License CP -Construction
2. Figure 2, Modified South Texas Project


Permit
TDAFWP Steam Supply and Exhaust System


\,-IN 93-51 July 9, 1993 This information
3. List of Recently Issued NRC Information Notices


notice requires no specific action or written response.
*SEE PREVIOUS CONCURRENCE


If you have any questions
OFFICE  *OGCB:DORS      *DRP:RIV    *TECH ED.    *SC:DRP:RIV    *D:DRP:RIV


about the information
NAME      PCWen/vsb  l MASatorius    MFMejac      WDJohnson      ABBeach


in this notice, please contact one of the technical
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


contacts listed below or the appropriate
LEKokaJko      CEMcCracken        ACThadani    GHMarcus          dd____
  06/08/93      06/09/93            06/10/93      06/16/93 DOCUMENT NAME: 93-51.IN


Office of Nuclear Reactor Regulation (NRR) project manager.orig /s/'d by BKGrimes Brian K. Grimes, Director Division of Operating
IN 93-xx


===Reactor Support Office of Nuclear Reactor Regulation===
June xx, 1993 This information notice requires no specific action or written response. If
Technical


contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachments:
you have any questions about the information in this notice, please contact
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
one of the technical contacts listed below or the appropriate Office of


OFFICE *OGCB:DORS
Nuclear Reactor Regulation (NRR) project manager.


*DRP:RIV *TECH ED. *SC:DRP:RIV
Brian K. Grimes, Director


*D:DRP:RIV
Division of Operating Reactor Support


NAME PCWen/vsb
Office of Nuclear Reactor Regulation


l MASatorius
Technical contacts:    Mark A. Satorius, RIV


MFMejac WDJohnson
(817) 860-8141 William D. Johnson, RIV


ABBeach DATE 06/01/93 l 06/02/93 06/02/93 06/04/93 06/04/93*PM:PDV:NRR
(817) 860-8148 Peter C. Wen, NRR


*C:SPLB:DSSA:NRR
(301) 504-2832 Attachments:
1. Figure 1, Existing South Texas Project TDAFWP Steam Supply and Exhaust


*D:DSSA:NRR
System


*C:OGCB:DORS:NRR
2. Figure 2, Modified South Texas Project TDAFWP Steam Supply and Exhaust


D LEKokaJko
System


CEMcCracken
3. List of Recently Issued NRC Information Notices


ACThadani
*SEE PREVIOUS CONCURRENCE


GHMarcus dd____06/08/93 06/09/93 06/10/93 06/16/93 DOCUMENT NAME: 93-51.IN
OFFICE  *OGCB:DORS      *DRP:RIV      *TECH ED.   *SC:DRP:RIV    *D:DRP:RIV


IN 93-xx June xx, 1993 This information
N.ME      PCWen/vsb      MASatorius    MFMejac      WDJohnson      ABBeach


notice requires no specific action or written response.
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


If you have any questions
LEKokaiko      CEMcCracken      l ACThadani    GHMarcus(          r    lines


about the information
06/08/93      1 06/09/93            06/10/93      06//6/93            06/,z/93 DOCUMENT NAME: INTDAFWP.WP                                                      6


in this notice, please contact one of the technical
IN 93-xx


contacts listed below or the appropriate
June xx, 1993 This information notice requires no specific action or written response. If


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
you have any questions about the information in this notice, please contact


===Reactor Support Office of Nuclear Reactor Regulation===
one of the technical contacts listed below or the appropriate Office of
Technical


contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter (301)C. Wen, NRR 504-2832 Attachments:
Nuclear Reactor Regulation (NRR) project manager.
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
Brian K. Grimes, Director


OFFICE *OGCB:DORS
Division of Operating Reactor Support


*DRP:RIV *TECH ED. *SC:DRP:RIV
Office of Nuclear Reactor Regulation


*D:DRP:RIV
Technical contacts:   Mark A. Satorius, RIV


N.ME PCWen/vsb
(817) 860-8141 William D. Johnson, RIV


MASatorius
(817) 860-8148 Peter C. Wen, NRR


MFMejac WDJohnson
(301) 504-2832 Attachments:
  1. Figure 1, Existing South Texas Project TDAFWP Steam Supply and Exhaust


ABBeach DATE 06/01/93 06/02/93 06/02/93 06/04/93 06/04/93*PM:PDV:NRR
System


l *C:SPLB:DSSA:NRR
2. Figure 2, Modified South Texas Project TDAFWP Steam Supply and Exhaust


*D:DSSA:NRR
System


C:OGCB:DORS:NRR
3. List of Recently Issued NRC Information Notices


D LEKokaiko
*SEE PREVIOUS CONCURRENCE


CEMcCracken
OFFICE    *OGCB:DORS    *DRP:RIV      *TECH ED.  *SC:DRP:RIV    *D:DRP:RIV


l ACThadani
NAME      PCWen/vsb    MASatorius    MFMejac    WDJohnson      ABBeach


GHMarcus( r lines 06/08/93 1 06/09/93 06/10/93 06//6/93 06/,z/93 DOCUMENT NAME: INTDAFWP.WP
DATE      06/01/93     06/02/93     06/02/93   06/04/93       06/04/93 l


6 IN 93-xx June xx, 1993 This information
PM PDV:NRR


notice requires no specific action or written response.
LEKokaiko


If you have any questions
06/1 /93 P


about the information
CEMcCI


in this notice, please contact one of the technical
e


contacts listed below or the appropriate
J      E


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
dThadani


===Reactor Support Office of Nuclear Reactor Regulation===
BC:OGCB:DORS:NRR
Technical


contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachments:
GHMarcus
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
D:DORS:NRR


OFFICE *OGCB:DORS
BKGrimes


*DRP:RIV *TECH ED. *SC:DRP:RIV
06/ "/93          06/f/L93    06/  /93            06/  /93 DOCUMENT NAME:   INTDAFWP.WP


*D:DRP:RIV
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


NAME PCWen/vsb
.        .1                                                                                          P.02 IN 93-xx


MASatorius
Junt Xx, 1993 rhis iofwmtion notice requires no specific act on or written response.                          If


MFMejac WDJohnson
yew ton & questions about the information in his notice, please contact


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
*a of          tochnical contacts listed bolow or th                appropriate Office of


D:DORS:NRR
btlw lector Regulation (NRR) project manager


LEKokaiko
Brian K. Gripes, Director


CEMcCI J dThadani GHMarcus BKGrimes 06/1 /93 06/ "/93 06/f/L93 06/ /93 06/ /93 DOCUMENT NAME: INTDAFWP.WP
Division of OPerating Reactor Support


l
Office of Nuclear Reactor Regulation


06-S12-1119
Toc"ial contatts:            MKrk A. Satorius, RI'
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
                                      (817) 660-4141 William D. Johnton, RIV


notice requires no specific act on or written response.
(817) B6O-814B


If yew ton & questions
Peter C. Win NRR


about the information
(301) 504-28i2 fttocwtsz:1
      1.      fig" It Existing South Texas Project TDAfWP Steam Supply and Exhaust


in his notice, please contact*a of tochnical
9    t


contacts listed bolow or th appropriate
1.      FlKrp    2, Modified South Texas Project TDA4I P Steam Supply and Exhaust


Office of btlw lector Regulation (NRR) project manager Toc"ial contatts: Brian K. Gripes, Director Division of OPerating
S.stoe


===Reactor Support Office of Nuclear Reactor Regulation===
.       ist tf Recently Issued NRC Information Noice~s
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
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-                -------            -I


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U-   0r            a


IN 93-xx June xx, 1993 Page 3 of This information
:w : 1"TuAokIrP


notice requires no specific action or written response.
IN 93-xx


If you have any questions
June xx, 1993 Page 3 of


about the information
This information notice requires no specific action or written response. If


in this notice, please contact one of the technical
you have any questions about the information in this notice, please contact


contacts listed below or the appropriate
one of the technical contacts listed below or the appropriate Office of


Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Nuclear Reactor Regulation (NRR) project manager.


===Reactor Support Office of Nuclear Reactor Regulation===
Brian K. Grimes, Director
Technical


contacts: Mark A. Satorius, RIV (817) 860-8141 William D. Johnson, RIV (817) 860-8148 Peter C. Wen, NRR (301) 504-2832 Attachment:
Division of Operating Reactor Support
List of Recently Issued NRC Information


Notices_. __I OFFICE OGCB:DORS
Office of Nuclear Reactor Regulation


DRP:RIV TECH ED. SC:DRP:RIV
Technical contacts:         Mark A. Satorius, RIV


D:DRP:RIV NAME PCWen/vsb
(817) 860-8141 William D. Johnson, RIV


MASatorius
(817) 860-8148 Peter C. Wen, NRR


A. WDJohnson
(301) 504-2832 Attachment:


ABBeach DATE .06/ I /93 _ 06/ /93 06/-L193 f06/ /93 l 06/ /93....BC:SPLB:DSSA:NRR
===List of Recently Issued NRC Information Notices===
          _.                     __I


D:DSSA:NRR
OFFICE    OGCB:DORS        DRP:RIV        TECH ED.  SC:DRP:RIV    D:DRP:RIV


BC:OGCB:DORS:NRR
NAME      PCWen/vsb      MASatorius        A.        WDJohnson    ABBeach


D:DORS:NRR
DATE    .06/ I /93    _  06/  /93        06/-L193 f06/  /93    l 06/  /93
                                      . .                                  ..


CEMcCracken
BC:SPLB:DSSA:NRR        D:DSSA:NRR      BC:OGCB:DORS:NRR    D:DORS:NRR


ACThadani
CEMcCracken              ACThadani       GHMarcus            BKGrimes


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