ML19261F146
| 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) | |
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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.
(DISTRIEiJTION CODE AOO1)
FOR ACTION:
- P ~ 5 2.
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INTERNAL:
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CHECK **LTR ONLY(1)
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EXTERNAL:
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April 2h, 1978 3
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Director of :Tuclear Reactor Regulation Attn:
R. W.
Reid Chief
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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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