ML20033E069
| ML20033E069 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/28/1990 |
| From: | Nichols S Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MN-90-21, SEN-90-41, NUDOCS 9003080149 | |
| Download: ML20033E069 (2) | |
Text
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- MaineYankee.
niiilhIrfiFdnicity FoH MAINE SINC ( 1972 t
EDISON DRIVE
- AUGUSTA, MAINE 04336 * (207)022 4868 i
5 February 28, 1990 MN-90-21 SEN-90-41 UNITED STATES NUCLEAR REGULATORY COMMISSION.
Attention: Document Control Desk Washington, DC 20555' Referer.ces:
(a)
License No. DPR-36 (Docket No. 50-309)
(b) MYAPCo letter to USNRC dated March 11, 1981 (FMY-81-33)
Subject:
Annual Report of Facility Changes and Relief and Safety Valve Failures and Challenges Gentlemen:
In accordance with 10 CFR 50.59, attached is a report containing a - brief description of the facility change completed at the Maine Yankee Atomic Power Station during-1989; and a summary of the safety evaluation for the change.
In Reference (b), Maine' Yankee ~ committed to reporting any challenges and/or-failures of PORV and pressurizer safety valves.
During _1989 there were no such
-events.
Very truly yours,
[f/.Echb S. E. Nichols Licensing Section Head-SEN:SJJ
' Enclosure.
c :-
.Mr. William T. Russell' Mr. Eric J. Leeds Mr. Cornelius F. Holden SEN9041.LTR
$0k $D 3
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4 Engineering Design Change Request 89-802 Modifications were made to two Motor Operated Valves (MOVs), PCC-M-42 and SCC-M-165.
The modifications included installation of a mid-span guide to reduce reach rod (between motor and valve) deflections and modifications to the motor operator limit switch arrangement to improve operational control.
This change did not increase the probability of occurrence or the consequences of r.n accident or malfunction of equipment important to safety previously evaluated, create the possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis or reduce the margin of safety as defined in the basis for any Technical Specification.
The change did not present an unreviewed safety question as defined in 10 CFR 50.59.
SEN9041.LTR
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