ML20072N892

RO 50-336/83-24:initial Insp of Reactor Vessel Internals on Core Barrel & Thermal Shield Revealed Damage to Thermal Shield.Damage Similar to That at Maine Yankee & St Lucie. Investigation Continuing

ML20072N892
Person / Time
Site:	Millstone
Issue date:	07/01/1983
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
MP-5176, RO-50-336-83-24, NUDOCS 8307180164
Download: ML20072N892 (1)

Text

NORTHEAST UTILITIES L L fhhh!h5-J %':::l'"'.1"',"%'l'ZT hfb$? ""' " "' '

July 1, 1983 Dr. 'Itaras E. Murley MP-5176 Regional Administrator, Region I U. S. Nuclear Regulatory Ca mission 631 Park Avenue King of Prussia, Pennsylvania 19406

Reference:

Facility Operating License No. DPR-65 Docket No. 50-336 Reportable Occurrence RO 50-336/83-24

Dear Dr. Murley:

This letter provides notification of Reportable Occurrence 83-24 pursuant to the requirements of Millstone Unit 2 Appendix A Technical Specifications, Section 6.9.1.8.i. This report concerns the discovery, during initial reactor vessel internals inspections, of conditions not specifically considered in the Safety Analysis Report or 'Ibchnical Specifications that may require renedial action or corrective measures to prevent the existence or developnent of an unsafe condition.

Initial inspections of reactor vessel internals on the core barrel and thermal shield reveal damage to the thermal shield that may be similar to the damage found during inspections at other similar facilities at the Maine Yankee and St. Lucie Plants.

The inspections are continuing and further information will be provided in the two week report.

Yours truly, NORIHEAST NUCLEAR ENERGY CCNPANY t

E. J. Mroczka Station Superintendent Millstone Nuclear Power Station EJM/RB:no cc: Director, Office of Managenent Information and Program Control, j Washington, D. C. (3)

U. S. Nuclear Regulatory Camission, c/o Document Management Branch, ,3 Washington, D. C. 20555 8307180164 830701 PDR ADOCK 05000336 q,1 S PDR

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