Information Notice 1990-39, Recent Problems with Service Water Systems
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555
June 1, 1990
NRC INFORMATION NOTICE NO. 90-39: RECENT PROBLEMS WITH SERVICE WATER SYSTEMS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is intended to alert addressees to potential problems
resulting from the failure of service water systems to provide an adequate and
reliable supply of cooling water-to safety-related structures, systems, and
components. It is expected that recipients will review the information for
applicability to their facilities and consider actions, as appropriatei, to
avoid similar problems. However, suggestions contained in this information
notice do not constitute NRC requirements; therefore, no specific action or
written response is required.
Description.of Circumstances:
On March 9, 1990, the licensee for the Clinton power plant reported problems
with the distribution of flow in the essential service water system. The staff
of the Nuclear Regulatory Commission (NRC) described those problems in Informa- tion Notice 90-26, "Inadequate Flow of Essential Service Water to Room Coolers
and Heat Exchangers'for Engineered Safety-Feature Systems." Recently, service
water system problems have been identified at seven other nuclear power plants.
On March 14, 1990, while both units were at full power, the licensee for the
Surry power plant performed a quarterly test on one of three diesel-driven
emergency service water pumps. After the diesel engine failed to start, the
licensee found that the dampers in the air supplies to all three engines were
closed. The engines started immediately when the dampers were opened.
At the Peach Bottom power plant, the emergency service water system is shared
by Units 2 and 3 and is supplied with water from the Susquehanna River. On
March 2, 1990, the NRC staff completed a safety system functional inspection of
the emergency service water system. The inspectors identified certain concerns
related to the capability of the system to perform its intended function. In
response, the licensee completed tests and an analysis of the system and
concluded that the system was operable with Unit 3 at power while Unit 2 was in
its scheduled mid-cycle outage with its emergency service water loads isolated.
On March 21, 1990, the licensee reported that emergency service water flows to
li-e
June 1, 1990
Page 2 of3
3 A
various Unit 2 components were inadequate for design basis conditions due to
accumulations of silt and corrosion products in the emergency service water
piping. Corrective actions by the licensee included inspection and cleaning of
piping and heat exchangers, throttling of the flow to the emergency diesel
generators to allow more flow to other components, and isolation of the flow to
redundant Unit 2 room coolers for emergency core cooling systems again to allow
more flow to other components. The licensee concluded that these actions
assured the operability of the emergency service water system with both Units 2 and 3 in operation.
An enhanced surveillance and test program for the emergen- cy service water system was implemented pending completion of replacement of
emergency service water piping for Unit 2 during the next refueling outage.
On March 23, 1990, while the River Bend power plant was in an outage, Region IV
reported continuing service water problems at the plant.
Use of acidic well
water when the system was first filled resulted in severe corrosion problems.
Water chemistry was corrected, and the acidic attack has stopped. 'However, microbiologically-induced corrosion has been present and is continuing. From
ultrasonic measurements, the licensee believes that the pitting rate is 24 mils
per year. The licensee plans to chemically clean the system or replace piping
as necessary.
During December, 1988, the licensee for the Haddam Neck power plant found that
the flow of service water to all four of the containment air coolers was
unacceptably low. The low flow was caused by a uniform buildup of silt and
corro-sin--rodu-tts--in-tbe-tubes-of-the cookeirs 7 r-Afr
the licensee cleaned the
tubes, the flow increased by approximately 50 percent.
On March 26, 1990,
during the current refueling outage, the licensee found that service water flow
to one of the two emergency diesel generators was less than- the manufacturer's
recommended value and that the heat removal rate for all of the containment air
coolers was several percent less than the value assumed in the accident analy- sis for the plant. The licensee intends to correct these problems before
returning to power.
In June, 1989, during a self-initiated assessment of the service water system, the licensee for the Farley power plant identified a potential design inadequa- cy concerning the flow of service water to safety-related loads during certain
accident scenarios.
The licensee reported the potential inadequacy and imple- mented compensatory measures pending further evaluation.
On March 27, 1990,
the licensee reported that their evaluation confirmed that during the accident
scenarios, service water flow to some safety-related loads would not be ade- quate without operator action.
The licensee has revised procedures as neces- sary to alert operators to the need for action if such events were to occur.
The Perry power plant has three emergency diesel generators and three service
water pumps for Unit 1. The pumps take suction on the forebay which receives
lake water through two traveling trash screens which are installed in parallel.
On April 3, 1990, Unit 1 was operating at full power when a gasket failed on
the discharge strainer for emergency service water pump A. Water spraying from
the strainer wetted several components including a control power transformer
and the motors for traveling screen A and screen wash pump A. Emergency
service water pump A and the emergency diesel generator that it cools were
IN 90-39 June 1, 1990 declared inoperable.
Further, screen wash pump B had been technically inopera- ble since November, 1989, pending delivery and installation of parts. However, emergency service water pump B was operating and screen B was clear.
At the Fitzpatrick power plant, on April 11, 1990, while the unit was in a
refueling outage, the licensee reported that silt had been found in check...
valves in emergency service water lines to the seal coolers for two pumps in
the residual heat removal system. The licensee concluded that the silt could
have prevented the residual heat removal system from fulfilling its safety
function.
i
Discussion:
On July 18, 1989, the NRC staff issued Generic Letter 89-13, Service Water
System Problems Affecting Safety-Related Equipment," to all holders of operat- ing licenses and construction permits for nuclear power plants. The letter
addressed continuing problems with service water systems in meeting the re- quirements of General Design Criteria 44, 45, and 46 ,in Appendix A of 10 CFR 50
and Section XI, "Test Control," in Appendix B of 10 CFR 50.
On April 4, 1990,
the NRC staff issued Supplement 1 to the generic letter. The supplement
contains questions from the industry that were posed during workshops held in
Philadelphia, Atlanta, Chicago, and Denver and the answers that were provided
by representatives of the NRC.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Char es E. Rssi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment:
List of Recently Issued NRC Information Notices
Attachent
111 939
June I, 1990
paop I of I
LIST o RtILt 15SUE
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90-38 Reqlrments for Procesting
5129/90
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Financial Assurance Submittals
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90-37 Sheared Palato Garvto-.Seft
1/24/9
All holders of Ms
Kas In Litttorqa Itetr
or Cps for naclear
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power reacters.
90-36 Apparent Felsificatin of
51/2/90
A11 holders of OLs
State Of Connecticut
or CPa for nuclear
Weight Certifiatns
ponr reactores and
10 Ctn 70 licensees.
90-S3 lransportatioe of Type A
5124/90
All l.S. RRC licansmn.
Quantities of Nom-Fissile
Radioactine Nsatrials
9034 Rponsae to False Sire"
5/1090
All holders of Oes
Act vnt~e"
or Cps for sucler
poer reactors.
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OnWPt
1/91 1
All holders of OLs
Ocupational Radiation
or CPs for nuclear
Exposurea at Spent Fuel
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90-32 Surface Creck and Subsurfac
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Indications Is the weld of
or CPs for suclear
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power reactors.
90-31 Update
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power reactors, fuel
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Reporting of Waste mishas
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555
OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
IPOSTAGE SP FEES PAIDI
LISNRCI
IN 90-39 June 1, 1990 declared inoperable.
Further, screen wash pump B had been technically inopera- ble since November, 1989, pending delivery and installation of parts. However, emergency service water pump B was operating and screen B was clear.
At the Fitzpatrick power plant, on April 11, 1990, while the unit was in a
refueling outage, the licensee reported that silt had been found in check
valves in emergency service water lines to the seal coolers for two pumps in
the residual heat removal system. The licensee concluded that the silt could
have prevented the residual heat removal system from fulfilling its safety
function.
Discussion:
On July 18, 1989, the NRC staff issued Generic Letter 89-13, "Service Water
System Problems Affecting Safety-Related Equipment," to all holders of operat- ing licenses and construction permits for nuclear power plants.
The letter
addressed continuing problems with service water systems in meeting the re- quirements of General Design Criteria 44, 45, and 46 in Appendix A of 10 CFR 50
and Section XI, "Test Control," in Appendix B of 10 CFR 50. On April 4, 1990,
the NRC staff issued Supplement 1 to the generic letter. The supplement
contains questions from the industry that were posed during workshops held in
Philadelphia, Atlanta, Chicago, and Denver and the answers that were provided
by representatives of the NRC.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Original Signed by
Charles E. Rossi
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment: List of Recently Issued NRC Information Notices
Document Name: IN 90-39
- SEE PREVIOUS CONCURRENCES
EAB:NRR*
TECH ED*
EAB:NRR*
PM:PD11:NRR* PM:PD12:NRR* PM:PD14:NRR*
RWoodruff
JMain
PBaranowsky DLaBarge
GSuh
AWang
5/15/90
5/16/90
5/21/90
5/17/90
5/17/90
5/17/90
PM:PD21:NRR* PM:PD22:NRR* PM:PD33:NRR* PM:PD4:NRR* PM:PD4:NRR* C:SPLB:NRR*
SHoffman
BBuckley
TColburn
PO'Connor
WPaulson
CMcCracken
5/17/90
5/16/90
5/17/90
5/16/90
5/17/90
5/18/90
C:EAB:NRR*
C:OGCB:NRR*
DFischer
CBerlinger
5/21/90
5/23/90
5,2
90
311a.in
IN 90-XX
May XX, 1990 declared inoperable. Further, screen wash pump B had been technically in- operable since November, 1989, pending delivery and installation of parts.
However, emergency service water pump B was operating and screen B was clear.
At the Fitzpatrick power plant, on April 11, 1990, while the unit was in a
refueling outage, the licensee reported that silt had been found in check
valves in emergency service water lines to the seal coolers for two pumps in
the residual heat removal system. The licensee concluded that the silt could
have prevented the residual heat removal system from fulfilling its safety
function.
Discussion:
On July 18, 1989, the NRC staff issued Generic Letter 89-13 to all holders of
operating licenses and construction permits for nuclear power plants. The
letter addressed continuing problems with service water systems in meeting the
requirements of General Design Criteria 44, 45, and 46 in Appendix A of
10 CFR 50 and Section XI, "Test Control," in Appendix B of 10 CFR 50.
On April
4, 1990, NRC issued Supplement 1 to the generic letter. The supplement con- tains questions from the industry that were posed during workshops held in
Philadelphia, Atlanta, Chicago, and Denver and the answers that were provided
by representatives of the NRC.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment: List of Recently Issued NRC Information Notices
Document Name: IN - WOODRUFF
CONCURRENCE:
- See previous copy for concurrences
EAB:NRR*
RWoodruff
5/15/90
TECH ED*
JMain
5/16/90
EAB:NRR*
PBaranowsky
5/21/90
PM:PD11:NRR*
DLaBarge
5/17/90
PM:PD12:NRR*
GSuh
5/17/90
PM:PD14:NRR*
AWang
5/17/90
PM:PD21:NRR*
SHoffman
5/17/90
C:EAB:NRR*
DFischer
5/21/90
PM:PD22:NRR*
BBuckley
5/16/90
C.OAtkRR
CBerlinger
5/$3/90
PM:PD33:NRR*
TColburn
5/17/90
PM:PD4:NRR*
PO'Connor
5/16/90
PM:PD4:NRR*
WPaulson
5/17/90
C:SPLB:NRR*
CMcCracken
5/18/90
D:DOEA:NRR
CERossi
5/ /90
311a.in
NRCIN 90-XX
May XX, 1990 parts.
However, emergency service water pump B was operating and screen B
was clear.
At the Fitzpatrick power plant, on April 11, 1990, while the unit was in a
refueling outage, the licensee reported that silt had been found in check
valves in emergency service water lines to the seal coolers for two pumps in
the residual heat removal system.
The licensee concluded that the silt could
have prevented the residual heat removal system from fulfilling its safety
function.
Discussion:
On July 18, 1989, the NRC staff issued Generic Letter 89-13 to all holders of
operating licenses and construction permits for nuclear power plants.
The
letter addressed continuing problems with service water systems in meeting
the requirements of General Design Criteria 44, 45, and 46 in Appendix A of
10 CFR 50 and Section XI, "Test Control," in Appendix B of 10 CFR 50.
On
April 4, 1990, NRC issued Supplement 1 to the generic letter.
The supplement
contains questions from the industry that were posed during workshops held in
Philadelphia, Atlanta, Chicago, and Denver and the answers that were provided
by representatives of the NRC.
This information notice requires no specific action or written response.
If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment:
List of Recently Issued NRC Information Notices
CONCURRENCE:
EAB:NRR*
RWoodruff
5/
/90
PM:PD21:NRR*
SHoffman
5/
/90
TECH ED*
JMain
5/
/90
- See previous copy for concurrences
W:DV
PM:PD11:NRR* PM:PD1.
Paranowsky DLaBarge
GSuh
5/. /90
5/
/90
5/
/9(
.2:NRR*
PM:PD22:NRR*
BMuckley
5/ /90
PM:PD33:NRR*
TColburn
5/
/90
PM:PD4:NRR*
PO-Connor
5/
/90
PM:PD4:NRR*
WPaulson
5/
/90
PM:PD14:NRR*
AWang
5/
/90
C: a
- NR
CMcCracken
51//190
__HRR
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.5/JJ/90
C:OGCB:NRR
CBerlinger
5/
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D:DOEA:NRR
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5/
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311a.in
NRCIN 90-XX
May XX, 1990 _a
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of servic wa
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At the Fitzpartick power plant, on April 11, 1990, while the unit was in a
refueling outage, the licensee reported that silt had been found in check
valves in ESW lines to the seal coolers for two pumps in the RFM system.
The
licensee concluded that the silt could have prevented the RHR system from
fulfilling its safety function.
piscussion- On July 18, 1989, the NRC staff issued Generic Letter 89-13 to all holders of
operating licenses and construction permits for nuclear power plants.
The
letter addressed continuing problems with service water systems in meeting
the requirements of General Design Criteria 44, 45, and 46 in Appendix A of
10 CFR 50 and Section XI, "Test Control," in Appendix B of 10 CFR 50.
On
April 4, 1990, NRC issued Supplement 1 to the generic letter.
The supplement
contains questions from the industry that were posed during workshops held in
Philadelphia, Atlanta, Chicago, and Denver and the answers that were provided
by representatives of the NRC.
This information notice requires no specific action or written response.
If
you have questions about the information in this notice, please contact the
technical contact listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Roger W. Woodruff, NRR
(301) 492-1180
Attachment:
List of Recently Issued NRC Information Notices
CONCURRENCE:
EAB: NILTECH ED
RWoodruff
- rAn
5/1jz90
5/1K X90
PM:PD:2 SHoBBckley
5/f7/90
5/t/90
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5/
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5/
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5/
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