Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate

Determination of Primary-to-Secondary Steam Generator Leak Rate

ML031070010
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
Issue date:	06/10/1994
From:	Grimes B Office of Nuclear Reactor Regulation
To:
References
IN-94-043, NUDOCS 9406060244
Download: ML031070010 (17)

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

/(Palo

In July 1992, the licensee for Palo Verde Nuclear Generating Station Unit 2 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

9406060244 fPfR Ite potace 94-otf 3 ito^2 L4: IZfq//

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

IN 94-43 June 10, 1994 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

94-42 Cracking in the Lower 06/07/94 All holders of OLs or CPs

Region of the Core for boiling-water reactors

Shroud in Boiling-Water (BWRs).

Reactors

94-41 Problems with General 06/07/94 All holders of OLs or CPs

Electric Type CR124 for nuclear power reactors.

Overload Relay Ambient

Compensation

94-40 Failure of a Rod Control 05/26/94 All holders of OLs or CPs

Cltlter Assembly to Fully for pressurized-water

Insrt Following a Reactor reactors (PWRs).

Trip at Braidwood Unit 2

94-39 Identified Problems in 05/31/94 All U.S. Nuclear Regulatory

Gamma Stereotactic Commission Teletherapy

Radiosurgery Medical Licensees.

94-38 Results of a Special NRC 05/27/94 All holders of OLs or CPs

Inspection at Dresden for NPRs and all fuel cycle

Nuclear Power Station and materials licensees

Unit 1 Following a Rupture authorized to possess spent

of Service Water Inside fuel.

Containment

94-37 Misadministration Caused 05/27/94 All U.S. Nuclear Regulatory

by a Bent Interstitial Commission Medical Licensees

Needle during Brachy- authorized to use brachy- therapy Procedure therapy sources in high-,

medium-, and pulsed-dose- rate remote afterloaders.

94-36 Undetected Accumulation 05/24/94 All holders of OLs or CPs

of Gas in Reactor for nuclear power reactors.

Coolant System

91-81, Switchyard Problems that 05/19/94 All holders of OLs or CPs

Supp. 1 Contribute to Loss of for nuclear power reactors.

Offsite Power

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.

orig /s/'d by BKGrines

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

• SEE PREVIOUS CONCURRENCES

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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

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

• SEE PREVIOUS CONCURRENCES

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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

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

• SEE PREVIOUS CONCURRENCES

OEAB:DORS SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

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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~r SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

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01/24/94 02/04/94 01/13/94 02/10/94 Email

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02/24/94 03/15/94 03/22/94 / /94 / /94

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TXK\PVINTK.PV2

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:DORi SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

• TKoshy 'k4 EGoodwin *BHolian *VNerses

ipEA0/94' 02/04/94 01/10/94 01/13/94 DRSS:RV OGCB:DORS PRPB:DRSS *C/OEAB:DORS

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01/24/94 02/04/94 01/13/94 02/10/94 Email

ADM/PUB C/PRPB:DRSS D/DRSS AC/OGCB:DORS D/DORS

• Tech Ed *LCunningham *FCongel AKugler BGrimes

02/24/94 3/15/94 3/22/94 / /94 / /94

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TXK\PVINTK.PV2

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; SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

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0295/9( 02/04/94 01/10/94 01/13/94 DRSS:RV OGCB:DORS PRPB:DRSS C/OEAB:DORS

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01/24/94 02/04/94 01/13/94 02/10/94 Email

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• Tech Ed Cut ham FCongel AKugler BGrimes

02/24/94 / /94 / /94 a, I -

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TXK\PVINTK.PV2

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 SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

• TKoshy EGoodwin *BHolian *VNerses

02/ /94 02/04/94 01/10/94 01/13/94 DRSS:RV OGCB:DORS PRPB:DRSS C/OEAB:DORS

• JReese *PCWen *TEssig *AChaffee

01/24/94 02/04/94 01/13/94 02/10/94 Email

ADM/PUB C/PRPB:DRSS D/DRSS AC/OGCB:DORS D/DORS

Tech Edo LCunningham FCongel AKugler BGrimes

02/Jfi194 02/ /94 02/ /94 02/ /94 02/ /94

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TXK\PVINTK.PV2

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, SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

• TKoshyaf, EGoodwin *BHolian *VNerses

02//0/94- 02/04/94 01/10/94 01/13/94 DRSS:RV OGCB:DORS PRPB:DRSS C/OEAB:DORS

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01/24/94 02/04/94 01/13/94 02/10/94 Email

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AKugler BGrimes

02/ /94 02/ /94

[OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TXK\PVINTK.PV2

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:DOR$W4 SC:OEAB:DORS PDIV-2:ADR4-5 PDII-4:ADR2

• TKoshy X EGoodwin *BHolian *VNerses

02/7 /94 02/04/94 01/10/94 01/13/94 DRSS:RV OGCB:DORS PRPB:DRSS C/o ( RS

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01/24/94 02/ /94 01/ /94 02//0/94 Email

AC/OGCB:DORS D/DORS

AKugler BGrimes

02/ /94 02/ /94 (OFFICIAL RECORD COPY]

DOCUMENT NAME: G:\TXK\PVINTK.PV2

IN 94- February 1994 Page 4 of 4 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

• SEE PREVIOUS CONCURRENCES

OEAB:DORS SC:OEAB:DOBS C:OEAB:DORS:NRR C:OGCB:DORS D:DORS:NRR

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01/10/94 01/13/94 01/24/94 02/4-/94 01/13/94 Email

DOCUMENT NAME: G:\TXK\PVINTK.PV2

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

• SEE PREVIOUS CONCURRENCES _a____________

OEAB:DORS I

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01/06/94 01/ /94 -v 01/ /94 ' 01/ /gJ

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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

one of the technical conta ts listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager

Bria K. Grimes, D ector

Divi ion of Oper ing Reactors

Offi of Nucle Reactor Regulation

Technical Contacts: Thomas Kosh

(301) 504-1 76 James Reese, R

(510) 975-02 Attachment: List of Recently I u d NRC Information Notices

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