ML15338A075

Pennsylvania State Univ. - Annual Operating Report for Period July 1, 2014 Through June 30, 2015

ML15338A075
Person / Time
Site:	Pennsylvania State University
Issue date:	11/23/2015
From:	Unlu K Pennsylvania State Univ, University Park, PA
To:	Document Control Desk, Office of Nuclear Reactor Regulation
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PENNSTATE KENAN UNLO, Ph.D.Director, Radiation Science and Engineering CenterProfessor, Department of Mechanical and Nuclear Engineering The Pennsylvania State University University Park, PA 16802-2304 Phone; (814) 865-6351Fax: (814) 863-4840E-mail: k-uilu(6psu edu SOENCE &ENGtNEER8'NG CENTERAnnual Operating Report, FY 14-15PSBR Technical Specifications 6.6.1License R-2, Docket No. 50-5November 23, 2015Attention:

Document Control DeskU. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001

Dear Sir or Madame:

Enclosed please find the Annual Operating Report for the Penn State Breazeale Reactor(PSBR) located at the Radiation Science and Engineering Center. This report covers theperiod from July 1, 2014 through June 30, 2015, as required by our Facility Operating License R-2 Appendix A Section 6.6.1.If you have any questions, please contact Mark Trump, Associate Director for Operations (814-865-6351).

Sincerely yours,Kenan U2nlUi, Ph.D.Director, Radiation Scienceand Engineering Center

Enclosures:

Annual Operating Report, FY 1 4-1 5cc: N.A. SharkeyA. ElnashaiA.A. AtchleyT.A. Litzinger J.A. LeaveyX. Yin -NRC0. Font -NRCD. Morrell-DOECollege of Engineering Collge o EnineeingAn Equal Opportunity University PENN STATE BREAZEALE REACTORAnnual Operating Report, FY 14-15PSBR Technical Specifications 6.6.1License R-2, Docket No. 50-5Reactor Utilization The Penn State Breazeale Reactor (PSBR) is a TRIGA Mark Ill facility capable of 1 MW steady stateoperation, and 2000 MW peak power pulsing operation.

Utilization of the reactor and its associated facilities falls into three major categories:

EDUCATION:

Several radiation laboratories at the facility provide support for graduate and undergraduate courses at the University as well as many high school classes that visit the reactor each year. Theseclasses cover topics such as Neutron Activation Analysis and identification of unknown samples,half-life determination, and nuclear security.

In total, the PSBR receives about 2500 visitors eachyear ranging from researchers to middle school students.

RESEARCH:

Much of the RSEC's usage supports research by reactor staff, professors, and graduate studentsfrom colleges throughout the University, and includes, for example, Radio-Chemistry applications, Neutron Imaging, and detector development.

SERVICE:The RSEC's unique facilities and employee skill-set support the National economy by serving industryand fulfilling domestic and global needs. For example, the RSEC has been involved in the production of radio-isotopes which enable the petro-chemical industry to run at full capacity; the facility's neutron beam laboratory provides material testing used in the quality control program for thePrimary Life Support Systems used by NASA; and fast-neutron irradiation fixtures support theNation's defense infrastructure and industry semiconductor production.

The PSBR facility operates on an 8 AM -5 PM shift, five days a week, with early morning, evening,and weekend shifts as-necessary to accommodate laboratory

courses, public education, University

Research, or Industrial service projects.

Page 1 of 6 PSBR Annual Operating Report, FY 14-15Summary of Reactor Operating Experience

-Technical Specification 6.6.t.a.Between July 1, 2014 and June 30, 2015, the PSBR was utilized as follows:Mode of Operation Time [hours] Time / Shift [hours / shift]Critical 925 3.18Sub-Critical 214 0.74Shutdown 1296 4.45Unavailable for Use 0 0Total Usage 2435 8.37The reactor was pulsed a total of 21 times with the following reactivities:

Reactivity Number of Pulses< $2.00 4$2.00 to $2.50 16> $2.50 1Total 21The square wave mode of operation was used 4 times to operate the reactor at power levelsbetween 100 and 500 KW.Total energy produced during this report period was 580.8 MWh with a consumption of 29.9 gramsof U-235.Unscheduled Shutdowns

-Technical Specification 6.6.1.b.During the reporting period, there were two unscheduled shutdowns resulting from reactor SCRAM.*On 3/17/15, the digital control system requested SCRAM during a startup at the FNI Tubewhen both facility exhaust fans momentarily lost power. Investigation revealed the fans hadlost power during a transfer from normal power to diesel generator power. The transferoccurred while testing the diesel following maintenance.

The power transfer is a "breakbefore make" function.

All systems performed as designed.

Minor changes to training andprocedures were implemented to prevent recurrence.

See AP-4 (2015-02) and AP-13 (2015-5)*On 6/23/15, while operating at 800 kW at the D20 tank, the digital control system requested SCRAM when it sensed both facility exhaust fans had shutdown.

Investigation revealed acontract painter had bumped the operating FES Hand/Auto switch to "off' position whilemoving equipment.

All systems performed as designed.

See AP-4 (2015-04)

Page 2 of 6 PSBR Annual Operating Report, FY 14-15Major Corrective or Preventative Maintenance with SafetySignificance

-Technical Specification 6.6.1.c.Routine preventative maintenance required by Technical Specifications (TS) was completed withinthe TS required time frames. The following safety related maintenance actions affecting reactorcontrol or safety equipment were also completed.

• On 12/22/14, the test circuit board assembly in the Power Range drawer of the ReactorSafety System was replaced with a spare following failure of the Fuel-i Reference Testbutton during the daily test. The Power Range drawer was then retested and functioned asdesigned.

• Various dates 2015, Emergency Exhaust System components were replaced to correctexcessive current draw observed during the extremely cold winter weather.

Corrective maintenance included replacement of the supply breaker, fan and motor bearings, and theuse of low temperature grease in the assembly.

• On 5/6/15, a rebuilt Transient Rod Shock Absorber was installed to correct binding in theabsorber.

The design function

-to absorb rod inertial and minimize shock on Transient Rodejection

-was preserved.

Major Changes Reportable Under 10 CFR 50.59 -Technical Specification 6.6.1.d.One change made at the facility in this year required a review and is reportable under 10 CFR 50.59:*In November of 2014, a modification package to install a hard stop in place of the Transient Rod Shock Absorber was completed after a 50.59 review confirmed the acceptability of themodification.

The temporary modification was installed to allow for rebuild of the shockabsorber following identification of binding during operations.

The screening determined this temporary modification had the potential to adversely affect the operation of the SSC.The subsequent review determined that ejection of the transient rod with the modification in place might result in damage to the component.

However, even if the damage resulted ina loss of function, no new event would be created and failure of the component to functionwas addressed in the design of the SSC. The possibility of rod ejection with the modification in place was eliminated by disabling the function in the digital control system and byadministrative restriction.

The Reactor Safeguards Committee has reviewed the 50.59document.

(See AP-12 2014-09 Removal of Transient Rod Shock Absorber)

Page 3 of 6 PSBR Annual Operating Report, FY 14-15Facility Changes of InterestAlthough the following modifications are not reportable under 50.59, they are notable and areprovided for information:

• In June of 2014, installation of core load 55a swapped the position of two similarly burned12 wt.% elements in the core layout. The swap was completed after element 221 wasobserved to have close tolerances during inspection.

The swap ensures element 221 can beremoved for followup inspection without difficulty.

The change had no discernable impacton the core performance.

(See AP-12 2014-4 Core 55a)*In July of 2014, the PSBR transitioned from core load 55a to core load 56. The changeencompassed four different groups of fuel movements and included loading 2 additional (for a total of 4) instrumented fuel elements into the core for future experiments.

Theloading pattern was generally symmetric and similar to past patterns.

Analysis showed thecore to be in compliance with Technical Specifications without encroachment to any limit.Pursuant to Technical Specification 2.2 the Safety System instrumented fuel element 1-17 (anew 12 wt. % element) was loaded such that it is in the position of Maximum Elemental Power Density.

Therefore, the LSSS set point is not required to be proportionally lowered.The table below compares key parameters for Core 55a and Core 56 at their most limitingpositions.

(See AP-12 2014-06 Core 56)Parameter Initial Core 55a Initial Core 56Total TRIGA Fuel Elements 102 105l2 wt% 37 388.5Swt% 65 67Excess Reactivity (at D20 Tank) $6.16 $6.66Power Defect at 1MW (at Ri) $3.42 $3.18Transient Rod Worth (at Ri) $3.03 $2.88Procedures Procedures are normally reviewed biennially, and on an as-needed basis. Numerous minor changesand updates were made to maintain procedures during the year and do not require a report under10 CFR 50.59.Page 4 of 6 PSBR Annual Operating Report, FY 14-15New Tests and Experiments In September of 2014, a new experimental structure was reviewed and approved for installation onthe west core face of the reactor.

The evaluation indicated the experimental structure would notsignificantly alter core power distribution or introduce an unanalyzed condition and did not requirea report per 10 CFR 50.59. The structure was placed in the core in March of 2015. (See AP-12 2014-08Westinghouse long-term irradiation)

Radioactive Effluents Released

-Technical Specification 6.6.1.e.LiquidThere were no planned or unplanned liquid effluent releases under the reactor license for thereporting period.Liquid radioactive waste, from the radiioisotope laboratories at the PSBR, is under the University byproduct materials license and is transferred to the Radiation Protection Office for disposal withthe waste from other campus laboratories.

Liquid waste disposal techniques include storage fordecay, release to the sanitary sewer per 10 CFR 20, and solidification for shipment to licenseddisposal sites.GaseousAll gaseous releases were less than 10% of the allowed concentrations and do not require specificreport.Argon-41 (4tAr)Gaseous effluent 41Ar is generated from dissolved air in the reactor pool water, air in dry irradiation tubes, air in neutron beam ports, and air leakage to and from the carbon-dioxide purged pneumatic sample transfer system.The amount of 41Ar released from the reactor pool is dependent upon the operating power level andthe length of time at power. The release per MWH is highest for extended high power runs andlowest for intermittent low power runs. The concentration of 41Ar in the reactor bay and the bayexhaust was measured by the Radiation Protection staff during the summer of 1986. Measurements were made for conditions of low and high power runs simulating typical operating cycles.For a conservative calculation of the 41Ar release, all power operations were assumed to take placeat the location of greatest generation and release (Fast Neutron Irradiator (FNI) tube). Thecalculation method includes direct release from the pool as well as release from the FNI fixture andestimates a production of ~2360 mCi for 580.8 MWh of operation during 2014-2015 fiscal year. Aportion of this 41Ar will decay in place however if all the 41A were released it represents less than 4%of the release limit.Page 5 of 6 PSBR Annual Operating Report, FY 14-15Parameter Argon-41 ProducedAverage concentration, unrestricted areaPermissible concentration, unrestricted areaPercentage of permissible concentration Calculated effective dose, unrestricted areaValue2,360<4x10-10lxlO-8<4.00<3.00Unitsmicro curiespCi/mliiCi/mlmRem/yrTritium (3H)Tritium is released by evaporation of reactor pool water as a gaseous release.

The total makeup tothe reactor pool in 2014-2015 was approximately 13,300 gallons or 1.52 gallons per hour. Theevaporative loss rate is dependent on relative

humidity, temperature of air and water, airmovement, etc.For an average pool tritium concentration of 35,400 pCi/I (average for July 1, 2014 to June 30, 2015),the Tritium activity released from the ventilation system would be "'1,780 pCi. A dilution factor of 2x 108 ml /sec was used to calculate the unrestricted area concentration.

This is from 200 m2 (cross-section of the building) times 1 rn/sec (wind velocity).

These are the values used for the safetyanalysis in the reactor license.Parameter Tritium releasedAverage concentration, unrestricted areaPermissible concentration, unrestricted areaPercentage of permissible concentration Calculated effective dose, unrestricted areaValue1,780<3x10-13lxl0-7<0.0003<2x10-4Unitsmicro curiesIpCi/mIm RemEnvironmental Surveys -Technical Specification 6.6.1.f.The only environmental surveys performed were the routine environmental dosimeters measurements at the facility fence line and two off-site control points (one residential area severalmiles away). The net measurements (in millirems) tabulated below represent the July 1, 2014 toJune 30, 2015 reporting period.Location 3rd Qtr '14 4th Qtr '14 1st Qtr '15 2nd Qtr '15 TotalFence North 3 5 2 5 15Fence South 4 6 4 5 19Fence East 1 4 1 6 12Fence West 2 6 4 6 18Pleasant Gap 0 0 0 3 3Child Care UP 0 0 0 2 2The exposures measured at all points on the facility fence-line were well within historical norms.Licensed operations remain well within the limits for the current fiscal year.Page 6 of 6 PENNSTATE KENAN UNLO, Ph.D.Director, Radiation Science and Engineering CenterProfessor, Department of Mechanical and Nuclear Engineering The Pennsylvania State University University Park, PA 16802-2304 Phone; (814) 865-6351Fax: (814) 863-4840E-mail: k-uilu(6psu edu SOENCE &ENGtNEER8'NG CENTERAnnual Operating Report, FY 14-15PSBR Technical Specifications 6.6.1License R-2, Docket No. 50-5November 23, 2015Attention:

Document Control DeskU. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001

Dear Sir or Madame:

Enclosed please find the Annual Operating Report for the Penn State Breazeale Reactor(PSBR) located at the Radiation Science and Engineering Center. This report covers theperiod from July 1, 2014 through June 30, 2015, as required by our Facility Operating License R-2 Appendix A Section 6.6.1.If you have any questions, please contact Mark Trump, Associate Director for Operations (814-865-6351).

Sincerely yours,Kenan U2nlUi, Ph.D.Director, Radiation Scienceand Engineering Center

Enclosures:

Annual Operating Report, FY 1 4-1 5cc: N.A. SharkeyA. ElnashaiA.A. AtchleyT.A. Litzinger J.A. LeaveyX. Yin -NRC0. Font -NRCD. Morrell-DOECollege of Engineering Collge o EnineeingAn Equal Opportunity University PENN STATE BREAZEALE REACTORAnnual Operating Report, FY 14-15PSBR Technical Specifications 6.6.1License R-2, Docket No. 50-5Reactor Utilization The Penn State Breazeale Reactor (PSBR) is a TRIGA Mark Ill facility capable of 1 MW steady stateoperation, and 2000 MW peak power pulsing operation.

Utilization of the reactor and its associated facilities falls into three major categories:

EDUCATION:

Several radiation laboratories at the facility provide support for graduate and undergraduate courses at the University as well as many high school classes that visit the reactor each year. Theseclasses cover topics such as Neutron Activation Analysis and identification of unknown samples,half-life determination, and nuclear security.

In total, the PSBR receives about 2500 visitors eachyear ranging from researchers to middle school students.

RESEARCH:

Much of the RSEC's usage supports research by reactor staff, professors, and graduate studentsfrom colleges throughout the University, and includes, for example, Radio-Chemistry applications, Neutron Imaging, and detector development.

SERVICE:The RSEC's unique facilities and employee skill-set support the National economy by serving industryand fulfilling domestic and global needs. For example, the RSEC has been involved in the production of radio-isotopes which enable the petro-chemical industry to run at full capacity; the facility's neutron beam laboratory provides material testing used in the quality control program for thePrimary Life Support Systems used by NASA; and fast-neutron irradiation fixtures support theNation's defense infrastructure and industry semiconductor production.

The PSBR facility operates on an 8 AM -5 PM shift, five days a week, with early morning, evening,and weekend shifts as-necessary to accommodate laboratory

courses, public education, University

Research, or Industrial service projects.

Page 1 of 6 PSBR Annual Operating Report, FY 14-15Summary of Reactor Operating Experience

-Technical Specification 6.6.t.a.Between July 1, 2014 and June 30, 2015, the PSBR was utilized as follows:Mode of Operation Time [hours] Time / Shift [hours / shift]Critical 925 3.18Sub-Critical 214 0.74Shutdown 1296 4.45Unavailable for Use 0 0Total Usage 2435 8.37The reactor was pulsed a total of 21 times with the following reactivities:

Reactivity Number of Pulses< $2.00 4$2.00 to $2.50 16> $2.50 1Total 21The square wave mode of operation was used 4 times to operate the reactor at power levelsbetween 100 and 500 KW.Total energy produced during this report period was 580.8 MWh with a consumption of 29.9 gramsof U-235.Unscheduled Shutdowns

-Technical Specification 6.6.1.b.During the reporting period, there were two unscheduled shutdowns resulting from reactor SCRAM.*On 3/17/15, the digital control system requested SCRAM during a startup at the FNI Tubewhen both facility exhaust fans momentarily lost power. Investigation revealed the fans hadlost power during a transfer from normal power to diesel generator power. The transferoccurred while testing the diesel following maintenance.

The power transfer is a "breakbefore make" function.

All systems performed as designed.

Minor changes to training andprocedures were implemented to prevent recurrence.

See AP-4 (2015-02) and AP-13 (2015-5)*On 6/23/15, while operating at 800 kW at the D20 tank, the digital control system requested SCRAM when it sensed both facility exhaust fans had shutdown.

Investigation revealed acontract painter had bumped the operating FES Hand/Auto switch to "off' position whilemoving equipment.

All systems performed as designed.

See AP-4 (2015-04)

Page 2 of 6 PSBR Annual Operating Report, FY 14-15Major Corrective or Preventative Maintenance with SafetySignificance

-Technical Specification 6.6.1.c.Routine preventative maintenance required by Technical Specifications (TS) was completed withinthe TS required time frames. The following safety related maintenance actions affecting reactorcontrol or safety equipment were also completed.

• On 12/22/14, the test circuit board assembly in the Power Range drawer of the ReactorSafety System was replaced with a spare following failure of the Fuel-i Reference Testbutton during the daily test. The Power Range drawer was then retested and functioned asdesigned.

• Various dates 2015, Emergency Exhaust System components were replaced to correctexcessive current draw observed during the extremely cold winter weather.

Corrective maintenance included replacement of the supply breaker, fan and motor bearings, and theuse of low temperature grease in the assembly.

• On 5/6/15, a rebuilt Transient Rod Shock Absorber was installed to correct binding in theabsorber.

The design function

-to absorb rod inertial and minimize shock on Transient Rodejection

-was preserved.

Major Changes Reportable Under 10 CFR 50.59 -Technical Specification 6.6.1.d.One change made at the facility in this year required a review and is reportable under 10 CFR 50.59:*In November of 2014, a modification package to install a hard stop in place of the Transient Rod Shock Absorber was completed after a 50.59 review confirmed the acceptability of themodification.

The temporary modification was installed to allow for rebuild of the shockabsorber following identification of binding during operations.

The screening determined this temporary modification had the potential to adversely affect the operation of the SSC.The subsequent review determined that ejection of the transient rod with the modification in place might result in damage to the component.

However, even if the damage resulted ina loss of function, no new event would be created and failure of the component to functionwas addressed in the design of the SSC. The possibility of rod ejection with the modification in place was eliminated by disabling the function in the digital control system and byadministrative restriction.

The Reactor Safeguards Committee has reviewed the 50.59document.

(See AP-12 2014-09 Removal of Transient Rod Shock Absorber)

Page 3 of 6 PSBR Annual Operating Report, FY 14-15Facility Changes of InterestAlthough the following modifications are not reportable under 50.59, they are notable and areprovided for information:

• In June of 2014, installation of core load 55a swapped the position of two similarly burned12 wt.% elements in the core layout. The swap was completed after element 221 wasobserved to have close tolerances during inspection.

The swap ensures element 221 can beremoved for followup inspection without difficulty.

The change had no discernable impacton the core performance.

(See AP-12 2014-4 Core 55a)*In July of 2014, the PSBR transitioned from core load 55a to core load 56. The changeencompassed four different groups of fuel movements and included loading 2 additional (for a total of 4) instrumented fuel elements into the core for future experiments.

Theloading pattern was generally symmetric and similar to past patterns.

Analysis showed thecore to be in compliance with Technical Specifications without encroachment to any limit.Pursuant to Technical Specification 2.2 the Safety System instrumented fuel element 1-17 (anew 12 wt. % element) was loaded such that it is in the position of Maximum Elemental Power Density.

Therefore, the LSSS set point is not required to be proportionally lowered.The table below compares key parameters for Core 55a and Core 56 at their most limitingpositions.

(See AP-12 2014-06 Core 56)Parameter Initial Core 55a Initial Core 56Total TRIGA Fuel Elements 102 105l2 wt% 37 388.5Swt% 65 67Excess Reactivity (at D20 Tank) $6.16 $6.66Power Defect at 1MW (at Ri) $3.42 $3.18Transient Rod Worth (at Ri) $3.03 $2.88Procedures Procedures are normally reviewed biennially, and on an as-needed basis. Numerous minor changesand updates were made to maintain procedures during the year and do not require a report under10 CFR 50.59.Page 4 of 6 PSBR Annual Operating Report, FY 14-15New Tests and Experiments In September of 2014, a new experimental structure was reviewed and approved for installation onthe west core face of the reactor.

The evaluation indicated the experimental structure would notsignificantly alter core power distribution or introduce an unanalyzed condition and did not requirea report per 10 CFR 50.59. The structure was placed in the core in March of 2015. (See AP-12 2014-08Westinghouse long-term irradiation)

Radioactive Effluents Released

-Technical Specification 6.6.1.e.LiquidThere were no planned or unplanned liquid effluent releases under the reactor license for thereporting period.Liquid radioactive waste, from the radiioisotope laboratories at the PSBR, is under the University byproduct materials license and is transferred to the Radiation Protection Office for disposal withthe waste from other campus laboratories.

Liquid waste disposal techniques include storage fordecay, release to the sanitary sewer per 10 CFR 20, and solidification for shipment to licenseddisposal sites.GaseousAll gaseous releases were less than 10% of the allowed concentrations and do not require specificreport.Argon-41 (4tAr)Gaseous effluent 41Ar is generated from dissolved air in the reactor pool water, air in dry irradiation tubes, air in neutron beam ports, and air leakage to and from the carbon-dioxide purged pneumatic sample transfer system.The amount of 41Ar released from the reactor pool is dependent upon the operating power level andthe length of time at power. The release per MWH is highest for extended high power runs andlowest for intermittent low power runs. The concentration of 41Ar in the reactor bay and the bayexhaust was measured by the Radiation Protection staff during the summer of 1986. Measurements were made for conditions of low and high power runs simulating typical operating cycles.For a conservative calculation of the 41Ar release, all power operations were assumed to take placeat the location of greatest generation and release (Fast Neutron Irradiator (FNI) tube). Thecalculation method includes direct release from the pool as well as release from the FNI fixture andestimates a production of ~2360 mCi for 580.8 MWh of operation during 2014-2015 fiscal year. Aportion of this 41Ar will decay in place however if all the 41A were released it represents less than 4%of the release limit.Page 5 of 6 PSBR Annual Operating Report, FY 14-15Parameter Argon-41 ProducedAverage concentration, unrestricted areaPermissible concentration, unrestricted areaPercentage of permissible concentration Calculated effective dose, unrestricted areaValue2,360<4x10-10lxlO-8<4.00<3.00Unitsmicro curiespCi/mliiCi/mlmRem/yrTritium (3H)Tritium is released by evaporation of reactor pool water as a gaseous release.

The total makeup tothe reactor pool in 2014-2015 was approximately 13,300 gallons or 1.52 gallons per hour. Theevaporative loss rate is dependent on relative

humidity, temperature of air and water, airmovement, etc.For an average pool tritium concentration of 35,400 pCi/I (average for July 1, 2014 to June 30, 2015),the Tritium activity released from the ventilation system would be "'1,780 pCi. A dilution factor of 2x 108 ml /sec was used to calculate the unrestricted area concentration.

This is from 200 m2 (cross-section of the building) times 1 rn/sec (wind velocity).

These are the values used for the safetyanalysis in the reactor license.Parameter Tritium releasedAverage concentration, unrestricted areaPermissible concentration, unrestricted areaPercentage of permissible concentration Calculated effective dose, unrestricted areaValue1,780<3x10-13lxl0-7<0.0003<2x10-4Unitsmicro curiesIpCi/mIm RemEnvironmental Surveys -Technical Specification 6.6.1.f.The only environmental surveys performed were the routine environmental dosimeters measurements at the facility fence line and two off-site control points (one residential area severalmiles away). The net measurements (in millirems) tabulated below represent the July 1, 2014 toJune 30, 2015 reporting period.Location 3rd Qtr '14 4th Qtr '14 1st Qtr '15 2nd Qtr '15 TotalFence North 3 5 2 5 15Fence South 4 6 4 5 19Fence East 1 4 1 6 12Fence West 2 6 4 6 18Pleasant Gap 0 0 0 3 3Child Care UP 0 0 0 2 2The exposures measured at all points on the facility fence-line were well within historical norms.Licensed operations remain well within the limits for the current fiscal year.Page 6 of 6