ML19210A148
| ML19210A148 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/27/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-0295, GQL-295, NUDOCS 7910240871 | |
| Download: ML19210A148 (3) | |
Text
- NRCFOnM 195 U.S. NUCLEAR REGULATORY P - MISSION DOCKET NUM BER 50-289
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'NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL
lCYDEh'T REPOR1 1t TO:
FROM:
OATE OF DOCUMENT J.
P. O'Reilly Metropolitan Edison Co 2-27-76 Reading, Penn. 19603 DATE RECEIVED R. C. Arnold 3-2-76 NUMBER OF C6 PIES RECEIVED ER ONOTORIZED PROP lNPUT FORM
[LjET 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 7 *"" )
DO NOT REMOVE __
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PLANT NAME* Three Mile Island #1 NCyrE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION /lNFORMATION ENVIRO BRANCH CHIEF:
Reid W/3 CYS FOR ACTION LIC. ASST:
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METROPOLITAN EDISON COMPANY POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 February 27, 1976 GQL 0295 Q
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ATTN:
Mr. R. W. Reid, Chief b
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,
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R. C. Arnold Vice President RCA:CWS:nh II I# #fV s
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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