ML19210A148

Event Rept 76-11/3L:on 760128 Steam Generator Pressure & Level Indicators Not Seismically Qualified Per FSAR Chapter 5.Cause Unknown.Instruments to Be Checked & Corrective Actions Taken If Not Seismically Qualified

ML19210A148
Person / Time
Site:	Three Mile Island
Issue date:	02/27/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
GQL-0295, GQL-295, NUDOCS 7910240871
Download: ML19210A148 (3)

Text

U.S. NUCLEAR REGULATORY P - MISSION DOCKET NUM BER

• NRCFOnM 195 50-289

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'NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL lCYDEh'T 1t REPOR1 FROM: OATE OF DOCUMENT TO:

J. P. O'Reilly Metropolitan Edison Co 2-27-76 Reading, Penn. 19603 DATE RECEIVED R. C. Arnold 3-2-76 ONOTORIZED PROP lNPUT FORM NUMBER OF C6 PIES RECEIVED

[LjET ER CORIGINAL O UNC LASSIFIE D OCOPy 1 signed' DESC RIPTIO N ,

ENCLOSURE Ltr trans the following: Event Report 76-11/3L on 1-28-76 commenting ou qualifications of Foxboro

& Bailey Instruments capability MCKNO W DCTC

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NCyrE: IF PERSONNEL EXPOSURE IS INVOLVED PLANT NAME* Three Mile Island #1 SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION /lNFORMATION ENVIRO BRANCH CHIEF: Reid

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Director of Nuclear Reactor Regulation b

V.s. eg.y'*lggure,7 7 ATTN: Mr. R. W. Reid, Chief '*",,

Operating Reactors Branch No. k U. S. Nuclear Regulatory Commission D gp' Washington, D.C. 20555 L Mr. J. P. O'Reilly, Director Office of Inspecticn and Enforcement, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19h06

Dear Sirs:

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Event Report 76-11/3L In accordance with Section 6.7 2.b.2 of the Technical Specifications for TMI-1, enclosed please find Event Report 76-11/3L. This repcrt is submitted in accordance with administrative controls technical specification 6.7.2.b.2 in effect prior to amendment 11 to the TMI-1 Operating License.

Sincerely,

,h i J I, R. C. Arnold Vice President RCA:CWS:nh II I# #fV s

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• 1490 060

Metropolitan Edison Company (Met-Ed)

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Event Report 76-11/3L Description of Event On January 28, 1976, it was determined that the Steam Generator (SG) pressure and level indicators may not have been seismically qualified as indicated in the TMI-l FSAR Chapter 5 page 5-5. Babcock and Wilcox (B&W) Topical Report BAW 10003 Rev. 4 indicates that some Foxboro and Bailey instruments have been seismically qualified but it is not known if these are the same type as those installed at TMI-1.

Designation of Apparent Cause of Event The cause of this event is not known.

Corr 2ctive Action The specific corrective actions to be taken fe r this event are not fully known in that it is not clear that a problem really exists. An investigation is in progress to determine if the TMI-1 instruments are seismically qualified and should it be determined that they are not qualified, further corrective action will be taken.

A follow-up to this report will be forwarded in 30 days to outline any additional corrective actions.

Instrument Data SG Level:

Designation: LT1-1A/B thru LTS-1A/B Make: Bailey Meter Type: BY 6241-A SG Pressure:

Designation: PT1-6A/B and PT2-6A/B Make: Foxboro Type: 611 GM-DSl with 610 AR power unit 1490 061