ML20203C008

Summary of 860404 Meeting W/Util & B&W Re Revised Core Loading Pattern.Dnbr & Peak Fuel Centerline Temp Increased But within Design Values for Plant

ML20203C008
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/15/1986
From:	Frank Akstulewicz Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8604180328
Download: ML20203C008 (12)

Text

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April 15,1986 bocketNo.: 50-213 Licensee: Connecticut Yankee Atomic Power Company Facility: Haddam Neck Plant Subject;

SUMMARY

OF APRIL 4,1986 MEETING WITH THE UTILITY REPRESENTATIVES CONCEPNING THE CYCLE 14 CORE RELOAD ANALYSES On April 4,1986, Connecticut Yankee Atomic Power Company met with the staff to describe the reanalyses to support Cycle 14 operation. The discussion focused on fuel mechanical and thermal-hydraulic analyses and accident and transient analyses. A copy of the presentation is enclosed.

The licensee stated that the revised cora loading pattern increased some key parameters, e.g., the departure from nucleate boiling ratio (DNBR) and the peak fuel centerline temperatures. However, in all cases the calculated values were within the design values for the plant. The licensee concluded their presentation by stating that no additions or revisions need to be made to the technical specifications requested by letter dated December 11, 1985.

The staff concluded that there did not seem to be any problems with the revised analyses. The staff stated it will review the revised reload report submitted April 3,1986 and complete its safety evaluation in order to support cycle 14 operation of the Haddam Neck Plant. The meeting was adjourned.

Original signed by: F. Akstulewicz Francis Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Enclosure:

DISTRIBUTION As Stated Docket File- FMiraglia NRC PDR ACRS(10) cc: See Next Page Local PDR NSIC ,

ISAP Reading OELD FAkstulewicz EJordan CGrimes BGrimes PAnderson ISAPD:DPL- IS )J ISAPD:DPL-FAkstulewicz:lt PArfeMon[ CGrimes 04//f/86 04/lO/86 04/6/86 8604100320 860415 PDR ADOCK 05000213 P PDR

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April 15,1986 Docket No.: 50-213 Licensee: Connecticut Yankee Atomic Power Company Facility: Haddam Neck Plant Subject;

SUMMARY

OF APRIL 4,1986 MEETING WITH THE UTILITY REPRESENTATIVES CONCERNING THE CYCLE 14 CORE RELOAD ANALYSES On April 4,1986, Connecticut Yankee Atomic Power Company met with the staff to

, describe the reanalyses to support Cycle 14 operation. The discussion focused on fuel mechanical and thennal-hydraulic analyses and accident and transient analyses. A copy of the presentation is enclosed.

The licensee stated that the revised core loading pattern increased some key parameters, e.g., the departure from nucleate boiling ratio (DNBR) and the peak fuel centerline temperatures. However, in all cases the calculated values were within the design values for the plant. The licensee concluded their presentation by stating that no additions or revisions need to he made to the technical specifications requested by letter dated December 11, 1985.

The staff concluded that there did not seem to be any problems with the revised analyses. The staff stated it will review the revised reload report submitted April 3,1986 and complete its safety evaluation in order te support cycle 14 operation of the Haddam Neck Plant. The meeting was adjourned.

Francis Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate Division nf PWR Licensing - B

Enclosure:

As Stated cc: See Next Page

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t Mr. John F. Opeka Connecticut Yankee Atomic Power Company Haddam Neck Plant Cc:

Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit Counselors at Law Department of Environmental City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent

.Haddam Neck Plant Richard M. Kacich, Supervisor RDF #1 Operating Nuclear Plant Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Edward J. Mroczka Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 State of Connecticut Office of Policy and Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Nuclear Power Station c/o U.S. MRC East Haddam Post Office East Haddam, Connecticut 06423 5

Regional Administrator, Region I U.S. Nuclear Regulatory Connission 631 Park Avenue ...

King of Prussia, Pennsylvania 19406

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CYCLE 14 RELOAD MEETING - APRIL 4, 1986 Name Organization F. Akstulewicz NRR/ISAPD C. Grimes NRR/ISAPD R. Lobel NRR/RSB-A J. Wilson NRR/RS8-A R. Karsch NRR/RSB-A L. Lois NRR/RS8-A

-T. N. Wampler B&W/ Fuel Engineer

8. J. Delano B&W/ Fuel Engineer C. F. McPhatter B&W/ Fuel Engineer W. M. Herwig NU/ Reactor Engineer G. P. van Noordennen NU/ Licensing G. Hsii NRR/RSB-A W. L. Brooks NRR/RSB-A' W. C. Lyon NRR/RS8-A

8. Mann NRR/RS8-A .

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HADDAM NECK CYCLE 14

. REDESIGN o NUCLEAR ANALYSIS o FUEL MECHANICAL ANALYSIS i

o FUEL THERMAL HYDRAULIC ANALYSIS -

o ACCIDENT AND TRANSIENT ANALYSIS l

o TECHNICAL SPECIFICATIONS l

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NUCLEAR ANALYSIS REDESIGN GOALS o

Meet all original Cycle 14 design requirements

~ o' -Minimize the number of prematurely discharged fuel assemblies o Minimize the additional burnup on the reinserted fuel assemblies o Minimize the potential for Technical Specification changes REDESIGN RESULTS

.a o All original Cycle 14 design requirements met

1) Major axis and quadrant symmetry maintained

2) Power peaking goals met Unrodded 1.362 (1.370) < 1.42 goal i Rodded 1.563 (1.423) 7 1.60 goal LTA nominal LHGR 9.86 (9.78) ][ 11.0 kw/f t goal

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o Four once burned fuel assemblies discharged (Batch 15A)

Four thrice burned fuel assemblies reir.serted (Batch 11) o Maximum EOC + 40 EFPD burnup 37,300 MWD /MTU Maximum Cycle 13 discharge burnup 37,6C0 MWD /MTU l

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FUEL MECHANICAL ANALYSIS o Confirmed previously analyzed cladding stress, strain, fatigue and collapse results with revised cycle design for all original fuel batches remain acceptable.

o Re-analyzed Batch 11 fuel for cladding stress, strain, ,

fatigue and collapse; qualified for fourth cycle.,..,

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FUEL THERMAL HYDRAULIC ANALYSIS o~

Confirmed that fuel-rod pressure remains less than nominal RCS pressure for all Batches.

o Limiting power distribution for MDNBR' evaluation less severe; MDNBR increased from 2.48 to 2.50 si s

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acceptable results transient analysis reviewed to confirm-

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Cycle redesign had small impact on physics parameters used in the accident and transient analyses l

o Cycle specific accident results compared to original cycle design; all results acceptable

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REVISED dRIGINAL i

Dropped Rod -

MDNBR 1.45 1.77 Fuel Centerline Temperature ~4411UF 4312UF l

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Fuel Centerline Temperature 4300 F 3650UF l

! Steamline -

Subcritical Break Margin 734 pcm 377 pcm Boron Dilution- Time to critical Refueling 1.16 hr 1.07 hr Startup 3.10 hr 2.88 hr Post Trip 65 min i

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• TECHNICAL SPECIFICATIONS o- Cycle'14 re'desigr.ed within all original Technical (i. Specification requirements o ho additional' Technical. Specification changes required

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