05000289/LER-1977-007, Forwards LER 77-007/01T.Provides Supplemental Info

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Forwards LER 77-007/01T.Provides Supplemental Info
ML19210A262
Person / Time
Site: Crane Constellation icon.png
Issue date: 05/23/1977
From:
METROPOLITAN EDISON CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19210A263 List:
References
GQL-0704, GQL-704, NUDOCS 7910250515
Download: ML19210A262 (4)
v • d • e


LER-1977-007, Forwards LER 77-007/01T.Provides Supplemental Info
Event date:
Report date:
2891977007R00 - NRC Website
v • d • e

text

NRC eonu 195 u.s. NUCLii An nECULATonY CF NIS3loN DOC V T *W M ef,p 5C-489 (2 7e1 N

NRC DISTRIBUTION con PART 50 DOCKET MATERIAL

'"'IgNE!;"TREPORT TO:

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FROM:

oATE oF oCCUMENT Metropolitan Edison Comm ny 5/23/77 Mr. J. P. O' Reilly Reading, Pa.

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J. G. Herbein 5/30/77 I

ETTEn ONoronizco enor iseurronu Nuuecn or copies nectiveo ALGIN AL M NC LAggg p t g p Ocorv

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3 / (o A,) h DESCniPTION ENCLoSunE Licensee Event Report (R0 50-289/77-07/1T) on 5/9/77 concerning both doors of the reactor building. emergency personnel access hatch 6

O NOT REMOVh '

ACKNOWLEDGED PLANT NAME:

(3-P: (1-P)

Three Mile. Island Unit No 1 NOTE:

IF PERSONNEL EXPOSURE IS INVOLVED RJL SEND DIRECTLY TO KREGER/J. COLLINS EOR ACTION /INFORMATION 4

BRANCH CHIEF:

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._.,r METROPOLIIAN EDISON COMPANY POST OFFICE BOX 542 READING PENNSYLVANI A 19603 TELEPWCNE 215 - 9294M1 c,

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May 23,197; i.

Regulatory Docket File C ' J 0 :z Mr. J. P. O'Reilly, Director 7'

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Office of Inspection and Enforcement, Region 1

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U. S. Nuclear Regulatory Cor:=ission

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631 Park Avenue C'4

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ing of Prussia, Pennsylvania 19406

Dear Sir:

Decket No. 50-289 Operating License No. DPR-50 In accordance with the Technical Specifications of our Three Mile Island Nuclear Statien Unit 1 (TMI-1), we are reporting the following reportable occurrence:

(1) 2.eport Number:

77-07/1T (2a) Required Report Date:

5-23-77 (2b) Date of Occurrence: 5-09-77 (3) Facility: Three Mile Island Nuclear Station - Unit 1 (b) Identificaticn o f Occurrence:

Title : Ecth dccrs of the reactor building emergency personnel access hatch were cpen at the same time.

Type :

A reportable occurrence as defined by Technical Specification 6 9 2.a. (2) in that both doors of the reactor building emergency personnel access hatch were open at the same time, thus leading to a loss of containment integrity as stated in section 17 when the ecnditions were as stated in section 3.6.1 of the Technical Specifications.

M76 M2 771520006

Sh'. J. P. O' Reilly, Director May 23, 1977 Office of Inspection and Enforce =ent, Region 1 GQL 070L (5) Ccnditions Prior to occurrence:

Power:

Core: 0 Elec. 0 6 RC Flcw:

102 x 10 lb/hr RC Pressure:

L90 psig RC Temp:

300 F PR2R Level:

100 inches PR2R Temp:

465 F (6) Description of Occurrence:

A maintenance man, while opening the inner dcor of the reactor building e=ergency perconnel access hatch, noticed that the cuter door was also partially open. He i==ediately re-closed the inner door and notified the Shift Foreman who investigated and returned the outer door in its closed pocition.

(7) Apparent Cause of Occurrence:

The cause of this occurrence has been determined to be both desien and personnel in that :

1) Attempting to clcse the decrs against an obstruction or too rapidly swinging the decr open and closed can cause excessive stress en the upper hinge shift extension causing it to bend, and thereby creating excessive door free-travel. The free-travel then allows violation of the door techanical interlock.
2) The upper hinge chaft extencion =ay not be adequately suppcrted (to take the strain frc= occasional dcor =isuse).

The manufacturer has propcsed an additional bearing be installed to provide additional support.

(8) Analysis of Occurrence:

Perscnnel at the scene i=nediately re-established containment integrity therefore, both decrs were open for less than ene minute.

The inner door seals were tight thus the occurrence did not constitute a threat to the health and safety of the public.

P.r. J. P. O'Reilly, Director May 23,1977 Office of Inspection and Enforcement, Region 1 GQL 070L (9) Corrective Acticn:

IMEDIATE:

1.

Returned the dcors to their closed positicn.

2.

Verified that the Control Rocm alar s for the reacter building doors functioned prcperly.

3 Restricted use of thie decr tc emergency use only.

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Performed dcor seal leakage test-satis factory.

LONG TERM:

A design change is being evaluated to install additional shaft support bearings and to provide an additional interlock device.

The Plant Operations Review Cor:mittee and Unit Superintendent have reviewed and approved the above corrective action and have taken steps to assure its completion.

(10) Failure Data:

Manufacturer - Chicago Bridge & Iron Cc.

Contract No. 2631U Gilbert Associates Hinged Shaft Extensicn - 2" steel shaft is part of hinge assembly.

Similar G.

  • rences:

74-11 7k-32 Sincerely, h '

J. G.

L rtein Vice President JGH:LGM:rk Attachment. Licensee Event Eeport 1476 G4

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