ML20055F370
| ML20055F370 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/10/1990 |
| From: | Trevors G NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CNSS907289, NUDOCS 9007160351 | |
| Download: ML20055F370 (4) | |
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L x4._ Nebraska Public Power District GENERAL OFFICE l
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U.S. Nuclear Regulatory Commission Attention - Document' Control Desk Washington, DC 20555
Reference:
I,etter from J. M. pilant to T. A. Ippolito, dated April 16,.19 /9, f
"Reloa6 4, Cycla 5 - Startup Physics Testing".
Subject:
Reload 13, Cycle 14 - Startup Physics Testing Cooper Nuclear Station
.i NRC Docket No. 50-298, DPR-46 Gentlemen:
This letter is to inform you that the acceptance criteria for the startup physics tests described in the Reference have been met for the recent Cycle ~14 startup.
Detailed. results of the testing are available at Cooper Nuclear l
,. Station for review, r
'I If you have any questions or require clarification on any of the tests, please call.
Sincerely, f
. Trevors Senior Staff Advisor l
Nuclear Power Group GAT:EAK:'sa Attachm9nt cc:
U.S. Nuclear Regulatory Commission L
Region IV Arlington, TX eh 9, [,l 11.
NRC Resident Inspector Cooper Nuclear Station pd l
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1.
CORE LOADING VERIFICATIOR 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 reactor core. At least one independent person must also either participate in performing the verification or review a videotape of the verification prior to startup.
III.
CRITERIA AND ACTION.S The as-loaded core must conform with the referenced core upon which the licensing analysis was performed.
Any discrepancies discovered in the loading will be promptly corrected and the affected areas reverified to be properly loaded prior to startup.
Conformance to the teFerenced loading will be demonstrated by a permanent core serial number map cnd 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 recoros of the verification are stored in the plant record file.
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2.
CONTROL ROD OPERABILITY AND SUBCRITICALITY CHEQE I.
PIIRPOSE This test ensures no gross local reactivity irregularities exist and all operable control rods are functioning properly.
II.
DESCRIPTION The control tod mobility test will be performed after the four bundles surrounding the given control rod are loaded.
The suberiticality check will be pettormed af ter the core loading has been comp'eted.
Performance of this test will provide assurance that criticality will not occur due to the wit.hdrawal of a single rod.
Each centrol rod in the core will be withdrawn and inserted one at a time to ensure its mobility with drive pressure. Also, the nuclear instrumentation will be monitored during the movement of each ccntrol rod to verify suberitic..lity.
III.
CRITERIA AND ACTIQtG 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 inoperabin 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 determine the caus,e.
IV.
SlHMARY OF RESUI.T1 All control rods moved satisfactorily under normal drive pressure and the core remaine, subcritical during the individual withdrawal of each control rod.
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3.
TIP STCNAL' UNCERTAINTY TEST
-I.
PURPOSE This' test determines the - Traversing In C%e Probe- (TIP) System total--
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-uncertainty using a statistical analysis.
II.
ESCRIPTION 1
Tocal _ TIP signci uncertainty consists of geometric and. random noise components.
Data to perform the analysis are obtained at intermediate' power levels-and/or ' power. levels greater than 75% with the reactor y
operating at steady state in an octant symmetric rod pattern (if possible).
f These data will be additionally used to perform a gross TIP.' symmetry checkiz
_ which is a. comparison-of integrated readings from symmetrically located -
1 TIPS.
- III, fRITERIA AND ACTIONS
.A.
The total TIP signal uncertainty '(random noise plus-geometric j
. uncertainties) fcr all data sets should bo 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
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control rod patterns.
In such cas.es, offline code predictions of l
exposuro_ or control rod induced asymmetry may prove useful' in o.
explaining the uncertainty.
a B.
The gross check of. TIP sigual symmetry lsbould 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 RESULTS A.
Two data cets were obtained for the total TIP uncertainty analysis.
- The total TIP uncertainty was determined to be 7.5% for the first data set and 2.1% for the second' data set.
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 7.9%
and 6.9%,
respectively. This is well within the 25% criterion.
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