Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C.
20555
June 10, 1994
NRC INFORMATION NOTICE 94-43: DETERMINATION OF PRIMARY-TO-SECONDARY STEAM
GENERATOR LEAK RATE
Addressees
All holders of operating licenses or construction permits for pressurized- water reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert licensees to problems that may exist in methods used to
determine steam generator primary-to-secondary leak rates that could lead to
the calculation-of unconservative leak rates.
It is expected that recipients
will review the information for applicability to their facilities and consider
actions, as appropriate, to avoid similar problems.
However, suggestions
contained in this information notice are not NRC requirements; therefore, no
specific action or written response is required.
Description of Circumstances
In July 1992, the licensee for Palo Verde Nuclear Generating Station Unit 2
/(Palo
Verde 2) noted a small steam generator tube leak by means of detectable
levels of activity in the secondary system.
By early February 1993, the
licensee observed an increasing trend in steam generator blowdown radiation
monitor activity.
On March 4, 1993, primary-to-secondary leakage in steam generator no. 2 increased rapidly.
At the same time, there was a small increase of 275 to
345 kilopascal (kPa) [40 to 50 psi] in reactor coolant system pressure because
of a charging pump surveillance test.
Using samples of steam generator
blowdown water analyzed for iodine-131 (1-131), the licensee estimated
primary-to-secondary leak rates of approximately 38 liters per day (lpd)
[10 gallons per day (gpd)].
Retrospective calculations based on readings from
the condenser vacuum exhaust radiation monitor and a xenon-133 (Xe-133) gas
grab sample, indicated that the leak rate had spiked to approximately 397 lpd
(105 gpd), gradually decreased, and stabilized at approximately 76 lpd
(20 gpd) two days later.
On March 14, 1993, while operating at 98-percent power, Palo Verde 2 experienced a steam generator tube rupture (SGTR) causing a primary-to- secondary leakage rate of approximately 908 liters per minute (lpm)
[240 gallons per minute (gpm)].
Before the tube rupture event, the licensee
had been measuring leak rates of approximately 15 to 38 lpd (4 to 10 gpd) in
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IN 94-43 June 10, 1994 Unit 2 steam generator no. 2 using samples from the blowdown line. An NRC
augmented inspection team (AIT) was dispatched to the site to review the
event. This event is further described in NRC Information Notice 93-56 dated
July 22, 1993.
Before the SGTR event, the licensee had used several different methods to
calculate primary-to-secondary leakage. The method the licensee used most
often involved measuring radionuclide activity (usually 1-131) in the steam
generators using samples from the blowdown line.
Station procedures did not
specify which method to use or require a verification of the leak rate by
performing a comparison.
On the basis of earlier tests, Combustion Engineering (CE) had concluded that
the steam generator blowdown samples were diluted by a factor ranging from
5 to 10 by feedwater 'spilling over" the center divider plate in the steam
generator. CE sent this information to the licensee in a letter dated
December 10, 1992. The CE letter stated that the downcomer samples were more
representative of steam generator bulk water than the blowdown samples.
The NRC staff reviewed the accuracy of calculating primary-to-secondary
leakage using samples from the blowdown line and concluded that this method
was inaccurate and had caused the licensee to underestimate the actual leakage
by as much as a factor of ten.
The underestimation occurred because feedwater
had diluted the steam generator blowdown samples.
Discussion
Failure to recognize the potential problems associated with the methods used
to calculate primary-to-secondary leak rates can lead to unconservative
estimates of the leak rate.
Early indications of a primary-to-secondary leak
can be obtained from several different locations, including the condenser off- gas radiation monitors, main steam line radiation monitors (particularly those
sensitive to N-16), and chemistry samples from the secondary side of the steam
generator. It is important to understand the limitations of any method used
in order to take appropriate actions to mitigate the consequences of a tube
leak or rupture.
The two most common methods for determining primary-to-secondary leak rates
are (1) sampling the secondary side of the steam generator for iodine and
(2) sampling feedwater for tritium.
Limitations associated with these methods
include hideout of the iodine within the steam generator, sample dilution by
incoming feedwater, changes to blowdown rate, and unaccounted tritium losses
in the secondary system. Hideout occurs when iodine from the primary coolant
selectively concentrates in structures within the steam generator after the
iodine transfers to the secondary coolant.
In System 80 steam generators
designed by CE, feedwater enters the steam generator on the cold-leg side and
is prevented from contacting the hot-leg side by a center divider plate.
However, the potential exists for feedwater to spill over the divider plate, enter the hot-leg blowdown line, and dilute the sample.
-' JIN 94-43 June 10, 1994 Using tritium to calculate primary-to-secondary leak rates involves a simple
mass balance of tritium in the secondary plant. Difficulties arise when
significant tritium loss mechanisms are either not accounted for or are not
well understood. One of these mechanisms is the loss of tritium in water
vapor through the condenser off-gas exhaust and leaking seals.
Additionally, methods of leak rate determination can lag significantly behind
the actual leak rate or can vary during power transients due to hideout
return.
The lag time is due to the inherent time delay in the circulation of
the water from the steam generator to the sample point.
Main steam line monitors designed for detecting N-16 are able to discriminate
between N-16 and other radiation and respond relatively rapidly in real time
to a steam generator tube leak. These monitors also have a continuous readout
in the control room, making it possible to track and trend the monitor
response.
Another method for detecting primary-to-secondary steam generator tube leakage
is through the use of on-line condenser off-gas monitors. When such monitors
are in service, they respond very rapidly to radiation from noble gases
associated with primary-to-secondary steam generator leaks. The response of
off-gas monitors can be continuously observed and their alarm setpoints can be
set to quickly respond even for small leaks, allowing operators to respond to
the alarm and take appropriate corrective actions.
Samples of the condenser
off-gas can be collected and subsequently analyzed to assist with leak rate
calculations; krypton (Kr) and xenon (Xe) are generally used for this purpose.
The common choice of isotope for this method is Xe-133. The accuracy of this
method is generally unaffected by the limitations that affect the other
methods.
On August 22, 1993, the operators at McGuire Nuclear Station Unit 1, shut down
the unit based on the early indications of a primary-to-secondary leakage.
While the plant was operating at full power, operators received radiation
monitor alarms from steam line nitrogen-16 (N-16) detectors and the condenser
air ejector radiation monitor. Chemistry samples confirmed primary-to- secondary leakage of 666 lpd (176 gpd) from steam generator A. Based on the
licensee's administrative limit of 190 lpd (50 gpd) leakage in any steam
generator, the licensee shut down the plant.
Subsequent licensee testing
revealed that there were eight tubes leaking with leak rates ranging from
7 lpd to 700 lpd (2 gpd to 185 gpd). The 700 lpd (185 gpd) leak was coming
through the upper joint of a sleeved tube.
This illustrates an appropriate
use of indications from one method to detect and other methods to quantify a
primary-to-secondary steam generator leak.
NRC Information Notice (IN) 94-05,
"Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves,"
provided further details on this event.
IN 91-43, "Recent Incidents Involving
Rapid Increases in Primary-to-Secondary Leak Rate," and IN 88-99, "Detection
and Monitoring of Sudden and/or Rapidly Increasing Primary-to-Secondary
Leakage," also discuss events where condenser air ejector monitors detected
abnormal steam generator leakage.
v-'
IN 94-43 June 10, 1994 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: Thomas Koshy, NRR
(301) 504-1176
James Reese, RIV
(510) 975-0237 Attachment:
List of Recently Issued NRC Information Notices
k achment
June 10, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
94-42
94-41
94-40
94-39
94-38
Cracking in the Lower
Region of the Core
Shroud in Boiling-Water
Reactors
Problems with General
Electric Type CR124
Overload Relay Ambient
Compensation
Failure of a Rod Control
Cltlter Assembly to Fully
Insrt Following a Reactor
Trip at Braidwood Unit 2
Identified Problems in
Gamma Stereotactic
Radiosurgery
Results of a Special NRC
Inspection at Dresden
Nuclear Power Station
Unit 1 Following a Rupture
of Service Water Inside
Containment
Misadministration Caused
by a Bent Interstitial
Needle during Brachy- therapy Procedure
Undetected Accumulation
of Gas in Reactor
Coolant System
Switchyard Problems that
Contribute to Loss of
Offsite Power
06/07/94
06/07/94
05/26/94
05/31/94
05/27/94
05/27/94
05/24/94
05/19/94
All holders of OLs or CPs
for boiling-water reactors
(BWRs).
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for pressurized-water
reactors (PWRs).
All U.S. Nuclear Regulatory
Commission Teletherapy
Medical Licensees.
All holders of OLs or CPs
for NPRs and all fuel cycle
and materials licensees
authorized to possess spent
fuel.
All U.S. Nuclear Regulatory
Commission Medical Licensees
authorized to use brachy- therapy sources in high-,
medium-, and pulsed-dose- rate remote afterloaders.
All holders of OLs or CPs
for nuclear power reactors.
All holders of OLs or CPs
for nuclear power reactors.
94-37
94-36
91-81, Supp. 1 OL = Operating License
CP = Construction Permit
IN 94-43 June 10, 1994 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.
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Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Thomas Koshy, NRR
(301) 504-1176
James Reese, RIV
(510) 975-0237 Attachment:
List of Recently Issued NRC Information Notices
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IN 94-XX
April xx, 1994 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
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Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
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Office of Nuclear Reactor Regulation
Technical contacts:
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(301) 504-1176
James Reese, RIV
(510) 975-0237 Attachment:
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IN 94-XX
April xx, 1994 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
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Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
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(301) 504-1176
James Reese, RIV
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IN 94-XX
March xx, 1994 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:
Thomas Koshy, NRR
(301) 504-1176
James Reese, RV
(510) 975-0237 Attachment:
List of Recently Issued NRC Information Notices
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March xx, 1994 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
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Technical contacts:
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(301) 504-1176
James Reese, RV
(510) 975-0237 Attachment:
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IN 94-XX
March xx, 1994 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:
Thomas Koshy, NRR
(301) 504-1176
James Reese, RV
(510) 975-0237 Attachment:
List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
OEAB:DOR;
- TKoshy 42.
0295/9(
SC:OEAB:DORS
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IN 94-XX
February xx, 1994
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:
Thomas Koshy, NRR
(301) 504-1176
James Reese, RV
(510) 975-0237 Attachment:
List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
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02/ /94 SC:OEAB:DORS
EGoodwin
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IN 94-XX
February xx, 1994
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:
Thomas Koshy, NRR
(301) 504-1176
James Reese, RV
(510) 975-0237 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
OEAB:DORS,
- TKoshyaf,
02//0/94- SC:OEAB:DORS
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02/04/94 PDIV-2:ADR4-5
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01/10/94 PDII-4:ADR2
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01/13/94 DRSS:RV
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01/24/94 Email
OGCB:DORS
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02/04/94 PRPB:DRSS
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AKugler
02/ /94 D/DORS
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02/ /94
[OFFICIAL RECORD COPY]
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IN 94-XX
February xx, 1994
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:
Thomas Koshy, NRR
(301) 504-1176
James Reese, RV
(510) 975-0237 Attachment:
List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
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02/7 /94 DRSS:RV
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SC:OEAB:DORS
EGoodwin
02/04/94 OGCB:DORS
J PCWen
02/ /94 PDIV-2:ADR4-5
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01/ /94 PDII-4:ADR2
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01/13/94 C/o (
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02/ /94 D/DORS
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IN 94- February
1994 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: Thomas Koshy, NRR
(301) 504-1176
James Reese, Region V
(510) 975-0237 Attachment: List of Recently Issued NRC Information Notices
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SC:OEAB:DOBS
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FtEGoodwin O
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IN 94- January
1994 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: Thomas Koshy, NRR
(301) 504-1176
James Reese, Region V
(510) 975-0237 Attachment: List of Recently Issued NRC Information Notices
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IN 94- January
1994 This information notice r quires no specific actio or written response. If
you have any questions ab ut the information in th s notice, please contact
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Nuclear Reactor Regulation (NRR) project manager
Bria K. Grimes, D ector
Divi ion of Oper ing Reactors
Offi
of Nucle
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Technical Contacts: Thomas Kosh
(301) 504-1 76
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