ML20092K094
| ML20092K094 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/20/1992 |
| From: | Horn G NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NSD920197, NUDOCS 9202250064 | |
| Download: ML20092K094 (4) | |
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GENER AL OFFICE P O BOX 499 COLUMBUS. NEliRA$KA 68602-0499 Nebraska Public Potver-District
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-__m-me NSD920197 February 20, 1992 1
U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
Reference:
Letter from J. M. Pilant to T. A. Ippolito, dated April 16, 1979, " Reload 4, Cycle 5 - Startup Physics Testing"
Subject:
Reload 14, Cycle 15 - Startup Physics Testing Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 Gentlemen:
The purpose of this letter is-to inform you that the acceptance criteria for the startup physics tests described in the Rclerence have been met for the recent Cycle 15 startup.
Summary of the test results are contained in the attachment.
Detailed results of the testing are available at Cooper Nuclear Station for review.
If you have any questions regarding these tests, please' contact my office.
Si ere y, ow
. Horn Nu ear PONor Group Manager GRH/dls Attachment cc:
NRC-Regional Administrator USNRC - Region IV Arlington,' TX NRC Resident Inspector Cooper Nuclear Station AAp/
9202250064 920220
.PDR ADOCK-05000298
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1.
CORE 1AADING VERIFICATION i
I.
PURPOSE This test visually verifies the core is loaded as intended.
II.
DESCRIPTION An underwater television camera or suitable viewing device will be employed to verify both proper orientation and location of each fuel assembly in the At least one independent person must also either participate reactor core.
l in performing the verification or review a videotape of the verification prior to startup.
III.
CRITERIA AND ACTIONS The as loaded core must conform with the referenced core upon which the performed.
Any discrepancies discovered in the licensing analysis was loading will be promptly corrected and the affected areas reverified te be properly loaded prior to startup.
Conformance to the referenced loading will be demonstrated by a permanent core serial number' map and documented by the signatures of the verifiers.
IV.
SUMMARY
OF RESULTS The as loaded core was found to conform exactly with the referenced core upon which the licensing analysis was performed. Permanent records of the verification are stored in the plant record file.
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1 2.
CONTROL ROD OPERABILITY AND SUBCRITICALJTY CHECK -
I.
PURPOSE-This test ensures no gross local reactivity irregularities exist and all operable control rods are functioning properly, 11.
DESCRIPTION The control rod mobility test will be performed af ter the four bundles surrounding the given control rod are loaded.
The suberiticality check will be performed af ter the core _ loading has been completed,_ _ Performance of this test will provide assurance' that-criticality will not occur due to J
the withdrawal of a single rod.
Each control rod in the core will be withdrawn and inserted one at a time to ensure its mobility with drive Also, the nuclear instrumentation will be monitored during the pressure.
movement of each control rod to verify suberiticality.
III.
CRITERIA AND ACTIONS For those control rods that will not move under normal drive pressure, appropriate repairs or adjustments will be made so that the drive pressure criteria can be met or the rod will be declared inoperable _ as described in the Technical Specifications.
If criticality were to be achieved by the withdrawal of a single control rod, the control rod would be inserted and all further rod movements: would cease and an investigation would be conducted to decermine the cause.
IV,
SUMMARY
OF RESULTS All control rods moved satisfactorily under normal drive pressure and the core remained suberitical during the individual withdrawal of each control rod.
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4 3.
I]P SIGNAL-UNCERTAINTY TEST I.
PURPOSE This test determines the Traversing In Core Probe (TIP) System total uncertainty using a statistical analysis.
11.
DESCRIPTION Total TIP signal uncertainty consists of geometric and random noise i
components.
Data to perform the analysis are obtained at intermediate power levels and/or power levels greater than 75%-vith the reactor.
operating at steady state in an octant symmetric rod pattern (if' possible).
These data will be additionally used to perform'a gross TIP
,ymmetry check, which is a comparison on integrated readings from symmetrically located TIPS.
111.
CRITERIA AND ACTIONS A.
The total TIP signal uncertainty (random noise-plus geometric uncertainties) for all data sets Eshould be less than 9%.
A minimum of two or up to six data sets may be used-to meet the above criterion.
If the 9% criterion is not met and the calculations have been' rechecked, the calibration of TIP system (e.g., axial alignment) shall be checked _
It may be necessary to omit data pairs from the analysis if-the exact octant symmetry is not attainable in fuel loading or control rod-patterns.
In such cases, offline code predictions of exposure or' control rod induced asymmetry.may prove useful in explaining the uncertainty.
B.
The gross check of SIP signal symmetry should yield a maximum deviation between symmetrically located pairs of-less than 25%.-
-If the criterion cannot be met, the' cause of the asymmetry must be investigated and an explanation attempted per Criterion A.
IV.
SUMMARY
OF RESUI,TS A.
Two data-sets were obtained for the total TIP uncertainty analysis. The total TIP uncertainty was determined to be 1.66%
-for the first data set and 1.56% for the:second data oct.
This is-well within the 9% criterion.
B.
Two data sets were used for the gross TIP symmetry analysis.
The gross TIP uncertainty was determined to be 3.55% and 3.52%-
.rospectively.
This is-well within the-25% criterion.
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