ML19339A445
| ML19339A445 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/12/1972 |
| From: | Minnick L YANKEE ATOMIC ELECTRIC CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8011030836 | |
| Download: ML19339A445 (3) | |
Text
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Proposed Change No. 103
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YANKEE ATOMIC ELECTRIC COMPANY n
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'lqi 20 TURNPIKE ROAD,WESTBORO, MASSACHUSETTS 01581
'M TELE PH O N E 617 366-90ll
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. UT October 12, 1972 United States Atomic Energy Commission 9
Washington, D. C.
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Attention:
Directorate of Licensing
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Reference:
License No. DPR-3 (Docket No. 50-29) 154::9
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Dear Sirs:
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Pursuant to Section 50-59 of 10 CFR Part 50, Yankee Atomic Electric Company hereby requests authorization to make the following change:
PROPOSED CHANGE: Reference is made to Section 107 of the license applica-tion, Core Instrumentation and particularly to the instrumentation location diagram on Page 107:3. We propose the following:
"To operate the reactor for *.he remainder of Core X with the north side instrumentation port sealed off which will result in a reduction of available flux wire paths from 19 to 8".
Reason for Change: Leakage has developed in one or more flux tubes below the seal plug area. As a result, boron deposition has rendered all paths in this instrument port inoperable.
The remaining thimbles, which pass through the east port, make it possible to insert flux wires to core positions G-5, H-2, H-5, H-8, J-3, J-4, J-5, and K-5, thus providing effective monitoring of essentially a one-eighth section of the core. A letter dated September 18, 1972 to the AEC sets forth Yankee's plan to replace the incore package and reactor head seal arrangement.
Description of Change:
(Refer to Page 107:4B of the FHSR). A primary seal will be effected by cutting off the top of the north port backup plug and TIG welding stainless steel plugs into the exposed tube ends.
A secondary seal vill consist of a 3" schedule 160 hemispherical pipe cap welded to the existing seal cap.
All fabrication, installation and testing cf this repair will be conducted in accordance with approved written procedures.
8011030k36 g
- c U. S. Atomic Energy Commission Proposed Change No. 103 Attn: Directorate of Licensing October 12, 1972 i
Safety Considerations: A comparison between analytical predictions and experimental data obtained during reactor operation has consist-ently shown the experimentally determined maximum hot channel factors to be significantly less than the predicted hot channel factors.
Methods have been developed for analyzing core power distribution using core outlet thermocouples data for radial power distribution and flux wire data for axial power distribution.
In this manner, hot channel factors in the core can be adequately determined using only a few flux wire positions in one quadrant of the core. The eight flux wire positions are adequate to permit continued use of this method.
It is our opinion that the Proposed Change does not present significant safety considerations not described or implicit in the license application,.as a= ended.
Scheduling of Change: The plant is scheduled to be shutdown October 20, 1972 to replace control rods. During this outage, provided approval is granted, the modifications described herein will be per-4 for=ed.
Respectfully submitted, YANKEE ATOMIC ELECTRIC COMPANY
.y m._at % m L. E. Minnick Vice President l
4 COMMONWEALTH OF MASSACHUSETTS)
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COUNTY OF 100RCESTER
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Then personally appeared before me, Lawrence E. Minnick, who, being duly sworn did state that he is a Vice President of Yankee Atomic Electric Company, that he_is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, q
and that the statements therein are true to the best of his knowledge-and belief.
j?/wt Mel
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Armand R. Soucy Notary Public My Commission Expires September 9, 1972
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GO DISTRIE*J2 ION FOR PART 50 DOCKET MATERIAL (TEMPORARY FO?S.)
CONTROL NO: '3689 FIIZ FROM:
DATE OF DOC:
DATE REC'D LTR IGMO RPT C/IEER Yer.kee Atcmic Electric Cc=pany V;stbom, Mass. 01581 L4 E. Minnick 10-12-79 10 18-79 X
TO:
,hPROPIEF0 INPUT NO CYS REC'D DOCKET NO:
CMSS:
X 40
'50-29 DEfrR.?2 ION:
ENCLOSURES:
Ltr sub=ittin6 pKposei '+"ge No.103 to Tech Specs, notatized 10-12-72.
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