Information Notice 1994-64, Reactivity Insertion Transient and Accident Limits for High Burnup Fuel

Reactivity Insertion Transient and Accident Limits for High Burnup Fuel

ML031060552
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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:	08/31/1994
From:	Burnett R, Grimes B NRC/NMSS/FCSS, Office of Nuclear Reactor Regulation
To:
References
IN-94-064, NUDOCS 9408250234
Download: ML031060552 (10)

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION&

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS

WASHINGTON, D.C. 20555 August 31, 1994 NRC INFORMATION NOTICE 94-64: REACTIVITY INSERTION TRANSIENT AND ACCIDENT

LIMITS FOR HIGH BURNUP FUEL

Addressees

All holders of operating licenses ok construction permits for nuclear power

reactors and all fuel fabrication 1 censees.

Purpose

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information

notice to alert addressees to recent information on high burnup fuel

performance that could affect previously approved fuel burnup limits and

enthalpy limits of highly exposed fuel. It is expected that recipients will

review the information for applicability to their facilities and consider

actions, as appropriate, to minimize adverse effect on design and operation of

reload cores and to properly evaluate their 10 CFR Part 21 reporting

responsibilities if continuing evaluation indicates limits should be reduced.

However, suggestions contained in this information notice are not NRC

requirements; therefore, no specific action or written response is required.

Description of Circumstances

Recent experimental data have suggested that high burnup fuel may be more

prone to failure during design-basis transients and reactivity insertion

accidents (RIAs) than previously thought. Recent data on the relationship

between fuel failure enthalpy and burnup for pressurized water reactor fuel

rods tested in foreign experimental facilities indicate lower failure

initiation enthalpy thresholds (measured in differential cal/gm) than was

considered in the evaluation of currently approved fuel burnup limits. The

NRC is closely following work to confirm the validity of the preliminary

results by verifying the conditions of the experimental tests. The NRC is

also reviewing data reduction, data interpretation, and the implications of

the observed failure results at low enthalpy rise levels on the safety

evaluation of LWR design-basis transients and accidents. The NRC is scheduled

to complete its review of the high burnup fuel data by the summer of 1995.

The results of this study may invalidate the basis for the previous staff

approvals of fuel design topical reports and fuel failure and fuel burnup

limits.

i. 'F. M A L( r

9408250234 ( -

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IN 94-64 August 31, 1994 Discussion

Recent information suggests that fuel rod damage during reactivity transients

can increase with high burnup. Various investigators have reported a "rim"

effect, consisting of a high burnup peripheral region of the fuel pellet, in

which the solid fuel matrix has a small grain size and is surrounded by

fission gas bubbles (Ref. 1). This porous microstructure could enable fuel to

disperse in powder form during transients that heat and expand the fission gas

bubbles.

A recent study for the Electric Power Research Institute (EPRI) was conducted

on fuel irradiated up to burnups of 60 GWD/MTU (Ref. 2). The objective was to

evaluate the degradation of mechanical properties in cladding and assembly

structural components caused by oxidation, hydriding, and radiation

embrittlement. While strength increases, ductility was found to be very low

and dependent on hydrogen content and fluence, both of which increase with

burnup. This appears to contradict a previous belief that metal annealing at

operating temperatures would prevent radiation damage from accumulating after

some initial period.

Recent integral tests with high burnup fuel under reactivity transient

conditions have indicated that the bounding peak fuel enthalpy that may cause

fuel cladding failure decreases significantly with increasing fuel exposure.

Of the fuel rods tested, the one with the highest burnup (approximately

65 GWD/MTU) failed at an enthalpy level of only 30 cal/gm with a reactivity

insertion corresponding to less than 15 cal/gm; some fuel dispersal may be

associated with this failure. An earlier integral test at the intermediate

burnup level of 32 GWD/MTU showed cladding failure at about 85 cal/gm

(Ref. 3). If the scatter of data points for high burnup failure is similar to

that observed in lower burnup failure data, the recent cited data are not

conclusive regarding the enthalpy failure limit for a specific fuel rod.

However, the transient data, the declining cladding ductility with increasing

burnup, and the fuel pellet "rim" effect, when considered together, suggest

that the trend of these results may be real.

LWR fuel suppliers and reactor operators (licensees) may wish to consider this

preliminary information in planning for fuel cycle designs, particularly those

fuel design changes and longer core operating cycles which may approach or

exceed approved fuel burnup limits. A higher burnup fuel may be required to

meet more restrictive enthalpy limits for fuel failure, fragmentation, and dispersal than those permitted by the acceptance criteria of the standard

review plan (Ref. 4). The NRC review of pending and future requests to extend

burnup beyond the limits previously approved for existing fuel designs (up to

approximately 60 GWD/MTU, fuel rod average) will more carefully consider the

adequacy of the reactivity insertion experimental data included or referenced

by such requests, until the implications of these high burnup experimental

data on licensing safety evaluations are resolved.

IN 94-64 August 31, 1994 On October 26, 1994, the NRC will present additional technical information on

this subject at the NRC 22 Water Reactor Safety Information Meeting.

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

you have any questions about the information inthis notice, please contact

one of the technical contacts listed below or the appropriate NRC project

manager.

Robert F. Burnett, Director ran K. I 3rimes Director

Division of Fuel Cycle Safety Division of Operating Reactor Support

and Safeguards Office of Nuclear Reactor Regulation

Office of Nuclear Material Safety

and Safeguards

Technical contacts: L. E. Phillips, NRR

(301) 504-3232 E. D. Kendrick, NRR

(301) 504-2891 J. Roth, NMSS

(301) 415-7257 Attachments:

1. References

2. List of Recently Issued NRC Information Notices

3. List of Recently Issued NMSS Information Notices

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Attachment 1 IN 94-64 August 31, 1994 REFERENCES

Rim

1. M. E. Cunningham, et al., "Development and Characteristics of the

Region in High-Burnup UO Fuel Pellets," Journal of Nuclear Materials, Vol. 188, page 19, June i992.

2. G. P. Smith, et al., "Hot Cell Examination of Extended Burnup Fuel

from Calvert Cliffs-1,' EPRI TR-103302, November 1993.

3. P. E. MacDonald, et al., Assessment of Light-Water-Reactor Fuel Vol.

Damage During a Reactivity-Initiated Accident," Nuclear Safety,

21 No. 5, September-October 1980.

4. "NRC Standard Review Plan," NUREG-0800, Rev. 2, July 1981.

Attachment 2 IN 94-64 August 31, 1994 LIST OF RECENTLY ISSUED

NRC INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

94-63 Boric Acid Corrosion of 08/30/94 All holders of OLs or CPs

Charging Pump Casing for pressurized water

Caused by Cladding Cracks reactors.

94-62 Operational Experience 08/30/94 All holders of OLs or CPs

on Steam Generator Tube for pressurized water

Leaks and Tube Ruptures reactors.

94-61 Corrosion of William 08/25/94 All holders of OLs or CPs

Powell Gate Valve Disc for nuclear power reactors.

Holders

94-60 Potential Overpressuriza- 08/22/94 All holders of OLs or CPs

tion of Main Steam System for pressurized-water

reactors.

94-30, Leaking Shutdown Cooling 08/19/94 All holders of OLs or CPs

Supp. 1 Isolation Valves at for nuclear power reactors.

Cooper Nuclear Station

94-59 Accelerated Dealloying of 08/17/94 All holders of OLs or CPs

Cast Aluminum-Bronze for nuclear power reactors.

Valves Caused by Micro- biologically Induced

Corrosion

94-58 Reactor Coolant Pump 08/16/94 All holders of OLs or CPs

Lube Oil Fire for pressurized water

reactors.

94-57 Debris in Containment 08/12/94 All holders of OLs or CPs

and the Residual Heat for nuclear power reactors.

Removal System

94-56 Inaccuracy of Safety Valve 08/11/94 All holders of OLs or CPs

Set Pressure Determinations for nuclear power reactors.

Using Assist Devices

OL = Operating License

CP = Construction Permit

Attachment 3 IN 94-64 August 31, 1994 LIST OF RECENTLY ISSUED

NMSS INFORMATION NOTICES

Information Date of

Notice No. Subject Issuance Issued to

94-47 Accuracy of Information 06/21/94 All U.S. Nuclear Regulatory

Provided to NRC during Commission Material

the Licensing Process Licensees.

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.

94-35 NIOSH Respirator User 05/16/94 All holders of OLs or CPs

Notices, "Inadvertent for nuclear power reactors, Separation of the Mask- and all licensed fuel

Mounted Regulator (MMR) facilities.

from the Facepiece on the

Mine Safety Appliances (MSA)

Company MMR Self-Contained

Breathing Apparatus (SCBA)

and Status Update"

94-23 Guidance to Hazardous, 03/25/94 All NRC licensees.

Radioactive and Mixed

Waste Generators on the

Elements of A Waste

Minimization Program

• V IN 94-64 August 31, 1994 On October 26, 1994, the NU will present additional technical information on

this subject at the NRC 22 Water Reactor Safety Information Meeting.

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 NRC project

manager.

Robert F. Burnett, Director Brian K. Grimes, Director

Division of Fuel Cycle Safety Division of Operating Reactor Support

and Safeguards Office of Nuclear Reactor Regulation

Office of Nuclear Material Safety

and Safeguards

Technical contacts: L. E. Phillips, NRR

(301) 504-3232 E. D. Kendrick, NRR

(301) 504-2891 J. Roth, NMSS

(301) 415-7257 Attachments:

1. References

2. List of Recently Issued NRC Information Notices

3. List of Recently Issued NMSS Information Notices

This information notice has been coordinated with MBCongdon of OIP.

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August xx, 1994 On October 26, 1994, the NRf will present additional technical information on

this subject at the NRC 22 Water Reactor Safety Information Meeting.

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 NRC project

manager.

Robert F. Burnett, Director Brian K. Grimes, Director

Division of Fuel Cycle Safety Division of Operating Reactor Support

and Safeguards Office of Nuclear Reactor Regulation

Office of Nuclear Material Safety

and Safeguards

Technical contacts: L. E. Phillips, NRR

(301) 504-3232 E. D. Kendrick, NRR

(301) 504-2891 J. Roth, NMSS

(301) 415-7257 Attachments:

1. References

2. List of Recently Issued NRC Information Notices

3. List of Recently Issued NMSS Information Notices

This information notice has been coordinated with MBCongdon of OIP.

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August xx, 1994 experimental data included or referenced in the submittal. On October 26,

1994, the NRC will present additional technical information on this subject at

the NRC 22n Water Reactor Safety Information Meeting.

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 contact(s) listed below or the appropriate NRC project

manager.

Robert F. Burnett, Director Brian K. Grimes, Director

Division of Fuel Cycle Safety Division of Operating Reactor Support

and Safeguards Office of Nuclear Reactor Regulation

Office of Nuclear Material Safety

and Safeguards

Technical Contacts: L. E. Phillips, NRR

(301) 504-3232 E. D. Kendrick, NRR

(301) 504-2891 J. Roth, NMSS

(301) 415-7257 Attachments:

1. References

2. List of Recently Issued NRC Information Notices

3. List of Recently Issued NMSS Information Notices

This information notice has been coordinated with MBCongdon of OIP.

• SEE PREVIOUS CONCURRENCE

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IN 94-XX

August xx, 1994 experimental data included or referenced in the submittal. On October 26,

1994, the NRC will present additional technical information on this subject at

the NRC 22nd Water Reactor Safety Information Meeting.

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 contact(s) listed below or the appropriate Office of

Nuclear Reactor Regulation (NRR) project manager.

Robert F. Burnett, Director Brian K. Grimes, Director

Division of Fuel Cycle Safety Division of Operating Reactor Support

and Safeguards Office of Nuclear Reactor Regulation

Office of Nuclear Material Safety

and Safeguards

Technical Contacts: L. E. Phillips, NRR

(301) 504-3232 E. D. Kendrick, NRR

(301) 504-2891 NMSS

(301) 415-xxxx

Attachments:

1. References

2. List of Recently Issued NRC Information Notices

This information notice has been coordinated with MBCongdon of OIP.

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