ML20056F716

Quad-Cities Nuclear Power Station,Unit 2 Cycle 13 Startup Test Results Rept

ML20056F716
Person / Time
Site:	Quad Cities
Issue date:	08/24/1993
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20056F713	List: ML20056F712 ML20056F716
References
NUDOCS 9308300297
Download: ML20056F716 (5)

Text

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b QUAD-CITIES NUCLEAR POWER STATION ,

UNIT 2 CYCLE 13 STARTUP TEST RESULTS '

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TABI.E OF CONTE!JTS i i

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i Test No. Title l i

1 Shutdown Margin  ?

2 Core Verification  !

3 Initial Critical I

4 TIP. Reproducibility and  !

Core' Power Symmetry .

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• 1.

Shutdown Marqin Demonstration and Control Rod Functional Checks Purreose The purpose of this test is to demonstrate for this core loading in the most reactive condition during the operating cycle, that the reactor is suberitical with the strongest control rod full out and all other rods fully inserted.

Criteria If a shutdown margin of 0.300% AK (=0.25% + R + B,C settling penalty) cannot be demonstrated with the strongest control rod fully withdrawn, the core loading must be altered to achieve this margin. The core reactivity has been calculated to be at a maximum at the beginning of cycle and R is given as 0.000% AK. The control rod B,C settling penalty for Unit Two is 0.05% AK.

Results and Discussion on May 5, 1993, control rod E-13 was fully withdrawn to demonstrate that the reactor would remain subcritical with the strongest rod out. This rod was calculated by GE to have the highest worth with the core fully loaded at the beginning of the cycle. The strongest rod out maneuver was performed to allow single control rod withdrawals for CRD testing.

Control Rod functional subcritical checks were performed as part of control rod friction testing. No unexpected reactivity insertions were observed when any cf the 177 control rods were withdrawn.

Nuclear Fuel Services (NFS) provided rod worth informetion for the two strongest diagonally adjacent rods D-12 and F-12 with rod E-13 fully withdrawn. This method provided an adequate reactivity insertion to demonstrate the desired shutdown nargin. On May 24, 1993, a diagonally adjacent shutdown margin demonstration was successfully performed.

Using the NFS supplied rod worth for E-13 (the strongest rod) and diagonally adjacent rod D-12, it was determined that with E-13 at position 48, and D-12 at position 20, a moderator temperature of 1130F, and the reactor subcritical, a shutdown margin of 1.082% AK was demonstrated. The NFS calculated shutdown margin with E-13 withdrawn and 6BoF reactor water temperature was 2.164% AK at the beginning of Cycle 13.

NFS's ability to determine rod worth was demonstrated by the accuracy of their in-sequence criticality prediction. The AK difference between the expected critical rod pattern and the actual critical rod pattern was determined to be 0.4632% AK af ter correcting for temperature and period.

This initial critical demonstrated that the actual shutdown margin at the beginning of cycle 13 was 2.6272% AK.

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, 2. Core '~erification Purpose i

Tne purpose of this test is to verify proper core location and orientation for each core fuel assembly.

Criteria l

l Prior to reactor startup, the actual core configuration shall be j verified to be identical to the planned core configuration. i i

Fesults and Discussion l The Unit Two Cycle 13 core was verified on May 4th, 1993. Fuel assembly

- orientation, seating, and ID serial number were verified for each  !

assembly. Two inspection passes were made over each assembly. The first pass was made to verify orientation and seating of assemblies.

The second pass was made to verify bundle ID numbers. A video camera

! was used during the inspection- All assemblies were found to be l prcperly seated and orientated in their designated locations.  ;

i on May 7, 1993, 4 fuel assemblies were reverified due to the unload and !

reload of 4 fuel assemblies for control rod J-15 drive replacement. Two passes were again made for orientation, seacing and ID verification.

All 4 assemblies were found to be properly seated and orientated in their designated location. l The bundle ID numbers arr shown in Figure 1.

3. Initial critical Prediction i

Purpose I The purpose of this test is to demonstrate Nuclear Fuel Services' (NFS) ability to calculate control rod worths and shutdown margin by predicting the insequence critical.

Criteria NFS prediction for the critical rod pattern must agree within 1% AK to actual rod pattern. A discrepancy greater than 1% AK will be cause for an On-Site Review and investigation by Nuclear Fuel Services.

Pesults and Discussion 4 I on May 26, 1993, at 0902 hours0.0104 days <br />0.251 hours <br />0.00149 weeks <br />3.43211e-4 months <br /> the reactor was brought critical with reactor water temperature at the time of criticality of 1840F. The AK difference between the expected critical rod pattern at 680F and the i actual critical rod pattern at 1840F was 0.005832 from rod worth tables ]

supplied by NFS. The temperature effect was -0.00008 AK from NFS supplied corrections. The excess reactivity yielding the 196 second  ;

1 positive period was 0.0004 AK. These reactivities resulted in a O.004632 AK difference (0.4632% AK) between the expected critical rod pattern and the actual rod pattern. This is within the 1% AK required in the criteria of this test, and NFS's ability to predict control rod worth is, therefore, successfully demonstrated.

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, 4. Corr

• Power Di nt ribt. tion Svmmetry Analysis Pu rpose The purpose of this test was to determine the magnitude of indicated core power distribution asymmetries using data (TIP traces and OD-1) collected in conjunction w!,th the CMC update.

Criteria A. The total TIP uncertainty (including random noise and geometric uncertainties obtained by averaging the uncertainties for all data sets) must be less than 9%.

B. The gross check of TIP signal symmetry should yield a maximum deviation between symmetrically located pairs of less than 25%.

Fesult s and Discussion Due to a forced outage and load demands, this portion of the test has  ;

not been completed. A supplement to this report will be issued upon  !

completion of the test. ,

t The expected issuance date of the supplement will be October 29, 1993.

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