ML20214A075
| ML20214A075 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/01/1987 |
| From: | Whittier G Maine Yankee |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 8663L-SDE, GDW-87-109, MN-87-55, NUDOCS 8705190239 | |
| Download: ML20214A075 (5) | |
Text
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MAIRE HARHEE MOMICPOWERCOMPARUe
,uaug,,Y,',,?u"g22s (207) 623-3521 0
10 CFR 50.59 May 1, 1987 HN-87-55 GDH-87-109 United States Nuclear Regulatory Commission Attention:
Document Control Desk Hashington, D. C.
20555
References:
(a)
License No. DPR-36 (Docket No. 50-309)
(b) HYAPCo Letter to USNRC dated March 11, 1981 (FHY-81-33)
Subject:
Annual Report of Facility Changes and Relief and Safety Valve railures and Challenges Gentlemen:
In accordance with 10 CFR 50.59, attached is a report containing a brief description of the facility changes completed at the Haine Yankee Atomic Power Station during 1986.
In Reference (b), Haine Yankee committed to reporting any chaIIenge; and/or failures of PORV and pressurizer safety valves. During 1986 there were no such events.
Very truly yours, HAINE YANKEE AT0 HIC POWER COMPANY bh/l i
G. D. Whittier, Hanager Nuclear Engineering and Licensing GDH/bjp Enclosure cc: Mr. Victor Norses, Acting Project Directorate I-3 Hr. Hilliam T. Russell Mr. Pat Sears Mr. Cornelius F. Holden i
070319C739 07050t POR ADOCK 03000309 H
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MAINE YANKEE ATOMIC POWER COMPANY DESIGN CHANGES IMPLEMENTED DURING 1986 EDCR 85-32
' Single failure proof rewiring of AC solenoid brakes on cranes EDCR 85-45 Loose parts monitoring system modifications EDCR 86-09 Desiccator addition to acid tank vents-1 i
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MAINE YANKEE ATOMIC POWER COMPANY EDCR 85-32 r
SINGLE FAILURE PROOF REHIRING OF AC SOLENOID BRAKES ON CRANES This change was implemented to ensure that the Reactor Containment Polar Crane, Turbine Hall Crane and Yard Crane would be able to support a load and the brakes would not fail to set in the event of a loss of one of the three phase power leads.
This was a simple wiring change to the non-nuclear-safety A.C. solenoid brakes.
This change improved the reliability of the cranes.
This change did not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated, create the possibility for 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. Accordingly, this change did not constitute an unreviewed safety question as defined by 10 CFR 50.59.
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MAINE YANKEE ATOMIC POWER COMPANY EDCR 85-45 l.00SE PARTS MONITORING SYSTEM MODIFICATIONS This change involved the relocation of some of the accelerometers and cables in the Loose Parts Monitoring System.
The modification was intended to reduce high background noise that was being picked up from the Control Element Drive Mechanisms and also to eliminate cable damage that occurred due to refueling activities.
This modification was implemented to improve operation of the Loose Parts Monitoring System which is non-nuclear-safety.
This change did not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated, create the possibility for 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.
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MAINE YANKEE ATOMIC POWER COMPANY e
EDCR 86-09 DESICCATOR ADDITION TO ACID TANK VENTS This modification involved the installation of desiccators in each Acid Tank Vent line to reduce moisture induction into the Acid Tanks and thus aid in corrosion reduction. At the same time overflow protection was added to the vent lines to eliminate the risk of acid overflowing and contaminating the desiccators.
This change improves the reliability of the Acid Tank Vents which are non-nuclear-safety.
This change did not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated, create the possibility for 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 constitute an unreviewed t,afety question as defined by 10 CFR 50.59.
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