ML19261F146

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Discusses Removal of Reactor Vessel Cavity Annulus Seal Ring & Relocation within Containment Bldg.Met Ed Concludes Possible Rupture of sand-filled Shield Plugs Unlikely If Properly Sealed.Sand Impingement Will Not Affect Sys
ML19261F146
Person / Time
Site: Crane 
Issue date: 04/24/1978
From: Herbein J
METROPOLITAN EDISON CO.
To: Reid R
Office of Nuclear Reactor Regulation
References
GQL-0758, GQL-758, NUDOCS 7910240805
Download: ML19261F146 (2)


Text

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--m REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIOUTION FOR INCCMING MATERIAL 50-289 REC: REID R W ORG: HEREEIN J O NRC DOCDATE: 04/24/TC METROPOL EDISON DATE FCVD: 05/02g DOCTYPE: LETTER NOTARIZED: NO IUBJEC T:

COPIES RECEI','ED FURNISHING ADDL LTP 1 ENCL 0 VE5SEL CAVITY ANNULUE.. INFO TO AFFLICANT"5 RESPONSE OF O2./21/78 CO ADVISING THE TMI-1 SEAL RING HAS GEEN MOVED CROM IT FREVIOUS NORMAL OFERATIONS POSITION AND RELOCATED TO AN AFEA WI REACTOR CONTAINMENT ELDG.

THE FLANT NAME: THREE MILE ISLAND - UNIT 1

REVIEWER INITIAL.

.LJM DISTRIGUTOR INITIAL:

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DI5TRIBUTION OF THIS MATERIAL IS AS FOLLOWS *****************+

GENERAL DISTRIEUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

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Director of :Tuclear Reactor Regulation Attn:

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Dear Sir:

Three Mile Island IIuclear Station, Unit 1 (T'II-1)

Operating License :To. DPR-50 Dcciet :To. 50-289 Reactor Vessel Cavity Annulus Metropolitan Ediscn Company letter of February 21, 1978, GQ.L 0282, in response to your letter of February 2,1978, stated that Met-Ed was con-sidering renoval and/or relecction of the cavity annulus seal ring during normal operations, and that Met-Ed intended tc resolve the issue prior to the Cycle h startup.

In addition, Mr. G. 3. Zwetzig of your staff, in-dicated that Met-Ed should address the consequences, if arv, of having the uand-filled shiell plugs rupture as a result of the postulated accident.

The TMI-l seal ring has been noved frca its previous normal cperations position and relocated to an area within the reactor containment building.

With regard to rupturing of the sand-filled shield plugs, Met-Ei has evaluated the consequences of the rupture and has determined that due to prcper sealing of essential cenponents, nc nechanical or electrical systers inside of ccn-tainment required after the accident will be affected by sand impingement.

It has also been determined thr t the presence of the sand vnl not clog essential equipment such as the reactor building spray nozzles, reactor building sump cr decay heat punps.

c'ncerely,

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/J.G.Herbein

/ 71 e President-Generaticn Y,

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