ML20198K952
| ML20198K952 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/28/1986 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| PY-CEI-OIE-0211, PY-CEI-OIE-211, NUDOCS 8606040173 | |
| Download: ML20198K952 (3) | |
Text
l$0 Tile CLEVELAND ELECTRIC ILLUMIN ATING COMP ANY P O BOX 5000 - CLEVELAND. OHIO 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLOG
- 55 PUBLICSO'JAAE Serving The Best Location in the Nation
[M-[
b MURRAY R. EDELMAN vice PatsiotNT v g Nuc u A n e
<g of' fern May 28, 1986 h
ih PY-CEI/01E-0211 L PAF FIL M ^w Mr. James G. Keppler Director, Region III Office of Inspection and Enforcement U.S.
Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Report of 10 CFR 50.59 Changes to the Initial Test Program
Dear Mr. Keppler:
Enclosed is a report of changes to the Initial Test Program made in accordance with Operating License Condition 2.C(4) and 10 CFR 50.59.
This report includes all such changes made since April 15, 1986 through May 27, 1986.
If you have any questions, please feel free to call.
Very truly ou s, d[4 Murray R. Edelman Vice President Nuclear Group MRE:njc Enclosure cc:
J. M. Taylor (39)
H. R. Denton J. Stefano J. Stiberg J. Grobe k\\
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Attachment PY-CEI/0IE-0211 L SAFETY EVALUATION MONTHLY
SUMMARY
1.
GENERAL INFORMATION FINAL APPROVAL FSAR DOCUKENT FSAR CR DATE SECr10N STI-003 86-065 04/30/86 14.2.10 II.
DESCRIPTION This safety evaluation was performed to evaluate a difference between STI-J11-003, Fuel Loading, Rev. 2, and FSAR 14.2.10 STI-J11-003, Fuel Loading was changed to add a section for inserting new neutron sources into the core. The added section directed the unloading of sixteen (16) fuel bundles from the reactor vessel, loading four (4) Californium-252 (Cf-252) sources into the vessel, and reloading the sixteen (16) fuel bundles into the vessel. Except for the small Cf-252 pin in each source, the sources are identical to the Antimony-Berylium sources previously installed in the core.
The following FSAR accidents were reviewed:
Misplaced Bundle Accident Control Rod Removal Error During Refueling The probability of a misplaced bundle was not increased, since essentially the same controls were in place that were used for the initial loading (Fuel Movement Checklist and STI-Jll-003).
The probability of a control rod withdrawal error during refueling was not increased because none of the refueling interlocks discussed in the FSAR were affected.
This safety evaluation covered the process of installing these sources.
The safety evaluation covering the use of the Cf-252 sources was included in the Design Change used to implement this installation.
III.
SUMMARY
The Fuel Loading instruction was changed to include the installation of four (4) additional Cf-252 neutron sources. Two types of FSAR accidents were reviewed explicitly: Misplaced Bundle Accident and Control Rod Removal Error During Refueling.
l The consequences of the above accidents were not affected.
1 1
I Attachment PY-CEI/0IE-02II L Antimony-Beryllum and Californium-Antimony-Beryllum neutron sources, fuel
' loading chambers, and intermediate range and sou'rce range neutron monitoring instrumentation will provide capability for neutron monitoring. Proper fuel assembly installation will be verified by visual inspection. Subcriticality checks will be performed by rod withdrawal for each just-loaded fuel cell as r
the core is loaded. A shutdown margin check will be performed during fuel loading after'144 bundles have been loaded, and again after fuel load has been completed. Inverse multiplication plots will be maintained during fuel j
loading. The partially loaded core will, at all times,~be suberitical by at least-0.38 AK/K with the analytically strongest rod withdrawn.
Initial criticality will be achieved during the full core shutdown margin
~
" test'." This test will be conducted with the reactor vessel open and with the intermedl Arn And source ranee neutron monicoring InsLautuestLestivas ope atabl e in a nunculucidwince mude Lv osa in on,hiah neutron level.
Critica15ty will be achieved by withdrawing control rods in the withdrawal sequence which contains the analytically highest worth rod.
N N
InitialfuelloadingandcritiS'alitywillbeperformedusingprocedures developed from Ceneral Electric Company supplied test specifications. Core alterations will be made with neutron instrumentation response of at least 0.7 counts per second and a signal-to-noise ratio of at least 2.0.
The Operating License, technical specifications and plant operating procedures, supplemented by startup test procedures, will govern plant operation to insure that the plant operates safely and as designed.
14.2.11 TEST PROCRAM SCHEDULE The Test Program Schedule is a det-ailed presedence network schedule which uses a computerized scheduling program to perform calculations. Information from the Test Program is input into the Integrated Project Schedule such that Construction and Test activities-cre compatible.
14.2-23