ML20126B650

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Summary of 820628-29 Meetings in Bethesda,Md Re RCS & Steam Generators.Attendee List Encl
ML20126B650
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 07/02/1982
From: Gray H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20126B295 List: ... further results
References
FOIA-84-897 NUDOCS 8506140167
Download: ML20126B650 (6)


Text

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C July 2, 1982 e

O- DOCKET NO. 50-289 MEMORANDUM FOR FILE n

THRU: Jacque P. Durr, Chief. M&PS

  • FROM: Harold Gray, Reactor Inspector, M&PS

SUBJECT:

MEETING IN BETHESDA 6/28-29/82 ONREACTORCOOLANTSYSTEM(RCS)AND STEAM GENERATORS (OTSG)

The meetirgs covered results of the reactor system internals inspection, cause of problem status and plans for work on steam generators and the corrosion relation between the two systems. The attendee's list is attached.

The documentation referenced and presented at the meetings is noted below:

TDR #343 by GPU of 6/14/82 - RCS Task 7 Appendix C - RCS inspections by GPU TDR #341 (draft copy) OTSG Failure Analysis (Preliminary)

TMI fl OTSG copy of slides presented on Failure Analysis and Data, by S.Giacobbe(GPU)

TMI #1 OTSG Status and Repair Process Description of 6/29/82

( As discussed by C. McCracken with NRC and consultants, attached is the 6/18/82 status update for TMI #1 steam generator corrosion study and repair. Of particular interest is the outline of consulting laboratories and their tasks.

Specific questions by Region I (H. Gray) included:

How to purge system of remaining sulpur OTSG Bubble Leak Test - What pressure gas (N2 ) l What is the maximum allowable sulfur level acceptable in the system prior to start up?

(4) What will prevent sulfur attack of the RCS and OTSG during pretest time.

heat up, testing, operations and the next wet layup.

(5) Where will blasting cap be located to detonate explosive? Answer - outside of steam generator head in a container to prevent mercury and copper contamination.

(6) Will tube length and therefore tube preload be changed by the explosive expansion process? Answer - the tube length will not be significantly changed by the process.

IN

SUMMARY

(1) RCS examination showed no cracking or defects attributable to sulfur assisted stress corrosion cracking.

(2) There are no known outstanding problems that would hinder successful steam generator repair that are not in the schedule with work proceeding for G resolution.

(3) The overview of the 0.T.S.G. repair sequence is to flush the tube-tubesheet crevice explosive from the tubes into the tube to tubesheet annulas to fom a seal, base line eddy current (E.C.) inspect a sample of tubes ( 1000),

hot full pressure test with a shutdown transient, cold wet layup and eddy 8506140167 850125 PDR FOIA ml DETJEN64-897 PDR

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E XET N0. 50-289/

N FOR FILt]; 2 i f.. current inspect preliminary to operational test cycle.

(4)Theexactlengthoftubetobeexplosivelyexpandedintothe tubesheet is still under consideration but is expected to be between 12-16".

(5) The main corrosion question is LF, or how remaining insoluble sulfur should be removed from the system internals.

(6)Atestexplosiveexpansionisplannedinafullsizesteamgenerator at Mount Vernon, Indiana during the week of 7/12/82.

D Narold Gray Reactor Inspector Enclosu m As stated b

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