ML20238C578

Forwards Cycle 10 Fuel Performance Rept Based on Month by Month Evaluation of I-131 Activity Data & Ultrasonic Insp of 136 Fuel Assemblies by Advanced Nuclear Fuels,Inc at End of Cycle 10

ML20238C578
Person / Time
Site:	Fort Calhoun
Issue date:	09/02/1987
From:	Andrews R OMAHA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-538, NUDOCS 8709100215
Download: ML20238C578 (20)

Text

_

4 Omaha Public Power District 1623 Harnetj Omaha, Nebraska 68102 2247 1

402/536-4000 l

September 2, 1987 LIC-87-538 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, DC 20555 I

Reference:

Docket No. 50-285 Gentlemen:

SUBJECT:

Cycle 10 Fuel Perforn,ance Report Pursuant to the requirement of Fort Calhoun Station Unit No. 1 Technical Speci-fication 5.9.3.h, Omaha Public Power District, holder of Facility Operating License No. DPR-40, submits the attached Fuel Performance Report for Cycle 10.

Sincerely, R. L. Andrews t

Division Manager

)

Nuclear Production RLA/rh Attachments c:

LeBoeuf, Lamb, Leiby 6 MacRae 1333 New Hampshire Avenue, N.W.

Washington, DC 20036 Mr. R. D. Martin, Regional Administrator Mr. A. Bournia, NRC Project Manager Mr. P. H. Harrell, NRC Senior Resident Inspector 0

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8709100215 870902 PDR ADOCK 05000285 p

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as sija i mploament w ith Icpiai oppunutory

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Fort Calhoun Station Cycle 10 FUEL PERFORMANCE REPORT

i Fort Calhoun Station Fuel Performance Report Cycle 10 As required by Fort Calhoun Station Technical Specification S.9.3.h, Omaha Pub-lic Power District is submitting a fuel performance summary.

The Cycle 10 fuel performance was based upon a month by month evaluation of I-131 Activity data (Figure 1) and an ultrasonic inspection of 136 fuel assemblies by Advanced Nuclear Fuels, Inc. (ANF) at the end of Cycle 10.

There were no observable Iodine spikes recorded, as evaluated on a daily basis, throughout Cycle 10 indicating no additional fuel failures.

The coolant activ-ity level was indicative of reinsertion of previous fuel failures.

It was esti-mated that there were two (2) to seven (7) failed fuel pins in the'25 GWD/T to 35 GWD/T burnup level.

These estimates were later confirmed by the ultrasonic fuel inspection.

During the 417 days of operation in Cycle 10 a total of 12,125 MWD /MTU was add-ed to the fuel in the core.

The batch average discharge burnup was 33,800 MWD /

MTU for the Batch H and Batch 1 assemblies in cycle 10.

This burnup level was comparable with the 34,200 MWD /MTU batch average discharge for the Batch G and Batch H fuel in Cycle 9.

The plant was operated at a 91.1 percent unit capa-city during Cycle 10.

ANF, under contract to OPPD, examined 136 fuel assemblies at the End of Cycle 10 operation. The 136 fuel assemblies were comprised of the 133 assemblies contained in the Cycle 10 core plus three (3) additional assemblies discharged from previous cycles which were either considered for reinsertion or reinserted in the Cycle 11 core.

Four (4) failed fuel rods were confirmed in the fuel contained in the Cycle 10 core with two (2) additional rods highly suspect.

One (1) failed rod was located in an assembly that was scheduled for reinser-tion in a later cycle.

The failed pins and locations are noted in Figures 2 through 7.

The three assemblies containing confirmed and suspected failures that were scheduled for reinsertion in to the Cycle 11 core were replaced with assemblies of nearly identical burnup and fissile content.

The replacement assemblies, which were either previously discharged or scheduled for discharge, were veri-fled to contain no failures.

Table 1 summarizes the historical core locations of the failed fuel assemblies.

Assembly HA22 is included in this report since it was not formally identified in the Cycle 9 fuel performance report. The historical core location was re-viewed to determine if there is any potential for a common mode failure as shown in Figures 8 through 14.

Boxes 98 and 40 were identified as historical locations for two assemblies, HA22/JA18 (98) and HA14/JA01 (40), however, fur-ther review has indicated that other fuel assemblies have resided in these loca-tions and have not failed, indicating that there is not a high degree of con-fidence or probability that a common mode failure mechanism exists in the Box 40 and 98 locations.

These inspections have successfully identified and removed failed fuel pins, however, the cause of these failures is currently unknown and can only be postulated as caused by mechanisms typical to the industry. Visual inspection of the Cycle 10 assemblies containing the identified failures and suspected failures is anticipated to take place in the fall of 1987 or winter of 1988.

.___-_____ a

After the visual examination of the fuel failures has been completed, an at-tempt to classify the failure mechanism will be made. Unfortunately without a destructive examination in a hot cell the root cause of the failure usually is unable to be determined, thus most failures will probably be classified as un-I known.

Other accomplishments in the fuel performance area during Cycle 10 were; the i

establishment of a Fuel Integrity Program, composed of key operation, technical support, fuel and QA personnel, to monitor and improve fuel performance, Ultra-sonic inspection of fuel at the end-of-cycle for failures and the substitution of intact fuel assemblies for all failures due for Cycle 11 operation and the

" vacuuming" of all foreign objects, which could lead to debris induced fail-ures, from the core support plate af ter core off load (12 such objects were i

located and removed).

The Company continues its association with EPRI and INPO in its efforts to improve fuel performance and reliability.

)

1 Initial performance of Cycle 11 looks very good.

Start completedwithcoolantactivity(I-131) averaging 2x10'ypoperationshavebeen Ci/gm and de-i creasing. The Fuel Reliability Indicator was calculated to be 0.0011 micro-curies / gram for July 1987 which is substantially below the 1987 INPO goal of 0.01 microcuries/ gram.

Thus, indications are no previous leakers have been re-l inserted for Cycle 11 operation and no fuel has failed.

)

TABLE 1 FUEL ASSEMBLY HISTORICAL LOCATIONS ASSEMBLY CORE LOCATION BY CYCLE NUMBER CYCLE 6 CYCLE 7 CYCLE 8 CYCLE 9 CYCLE 10

- CYCLE 11 llA14(1)(5)

Box 5(C-2)

Box 40(G-5)

Box 132(K-17)

N/A N/A N/A i

JA02(2)(5)

N/A N/A Box 133(M-17) Box 59(5-7)

Box 94(L-13)

N/A JA12(3)(5)

N/A N/A Box 111(C-15) Box 68(L-9)

Box 64(D-9)

N/A KA18(2)(5)

N/A N/A N/A Box 84(R-11) Box 87(T-12)

N/A JA01(2)(6)

N/A N/A Box 1(F-1)

Box 75(B-11) Box 40(G-5)

N/A JA18(3)(6)

N/A N/A Box 98(S-13)

Box 52(E-7)

Box 17(E-3)

N/A HA22(4)(7)

Box 98(S-13)

Box 28(E-4) Box 105(L-14) Box 73(A-9)

N/A N/A l

NOTES:

(1)

Considered for reinsertion in Cycle 12.

)

(2)

Scheduled for reinsertion for Cycle 11.

(3)

Scheduled for discharge at EOC 10.

(4) Discharged at EOC 9 - not identified in Cycle 9 Fuel Performance Report.

(5) Confirmed failure (UT).

(6) Suspect failure (UT).

(7) Confirmed failure (visual).

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