ML19290A455: Difference between revisions

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METROPOLITAN EDISON COMPANY 3as ciany or cerisast ruatic uritir:ec ccaranar.c: j
METROPOLITAN EDISON COMPANY 3as ciany or cerisast ruatic uritir:ec ccaranar.c: j
'OST CFFICE BOX 542  READING. PENNSYLVANI A 19603                            TELEPHONE 215 - 929 3601 July 12, 1973
'OST CFFICE BOX 542  READING. PENNSYLVANI A 19603                            TELEPHONE 215 - 929 3601 July 12, 1973 Mr. James P. O'Reilly Director, Division of Compliance U. S. Ato:ic Energy Co==issien Region 1 970 Broad Street Newark, New Jersey 07102
                                                                                                      .
Mr. James P. O'Reilly Director, Division of Compliance U. S. Ato:ic Energy Co==issien Region 1 970 Broad Street Newark, New Jersey 07102


==Subject:==
==Subject:==
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Verification Progra=
Verification Progra=
Docket No. 50-239
Docket No. 50-239
                                                                                                        .


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==

Latest revision as of 15:27, 1 February 2020

Final Deficiency Rept Re Completion of Valve Wall Thickness Verification Program.Wall Thickness of Valves Adequate. Records of Measurements & Evaluations Available at Site
ML19290A455
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 07/12/1973
From: John Miller
METROPOLITAN EDISON CO.
To:
Shared Package
ML19290A453 List:
References
NUDOCS 7911070633
Download: ML19290A455 (1)


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METROPOLITAN EDISON COMPANY 3as ciany or cerisast ruatic uritir:ec ccaranar.c: j

'OST CFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929 3601 July 12, 1973 Mr. James P. O'Reilly Director, Division of Compliance U. S. Ato:ic Energy Co==issien Region 1 970 Broad Street Newark, New Jersey 07102

Subject:

Three Mile Island Nuclear Station, Unit 1 Status of the Valve Wall Thickness .

Verification Progra=

Docket No. 50-239

Dear Mr. O'Reilly:

Your letter dated June 22, 1972 requested that we provide verifica-tion that valves over one_ inch nc=inal pipe size within the reactor coolant syste= boundary, as defined in 50.55(a) of 10 CFR 50, =eet the =ini=u= vall thickness requiremrits of specified codes and standards. Our letter to you dated July 21, 1972 described oOr plans and schedule for verifying wall thick-nesses of the subject valves and'for maintaining the records of the pertinent data at the site. This letter constitutes our final report as our valve vall thickness verification progra= has been ec=pleted.

A total of sixty-five. valves in Unit 1 l'arger than one inch nc=inal pipe size fall within the reactor coolant pressure boundary. Final =easure-cents have been ec=pleted on all sixty-five of these valves. Measure =ents of all valves show that the thicknesses =eet the standard, ANSI B16.5, specified in the purchase orders for these valves.

In su==ary, the valve wall thickness verification program for Unit 1 is co=plete and the valves have been found to have adequate vall thicknesses.

Records of our =easure=ents and evaluations are available at the site.

A Very truly,yotrs, J

j Y v*

J . G. Miller 1557 326

'V ' ce President brh CC: Mr. F. E. Kruesi, Director of Regulatory Operations Mr. W. A. Verrochi y 91106