ML20084H029

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Trip Rept of 830413 Fifth third-party Review Meeting in Parsippany,Nj Re Steam Generators.Ndt Acceptable.Minor Recommendations on Startup & Insp Procedures Provided
ML20084H029
Person / Time
Site: Crane 
Issue date: 04/21/1983
From: Benaroya V
Office of Nuclear Reactor Regulation
To: Johnston W
Office of Nuclear Reactor Regulation
Shared Package
ML20079G498 List:
References
FOIA-83-243, FOIA-83-A-18 NUDOCS 8304270380
Download: ML20084H029 (2)


Text

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MEMORANOUM FOR: William V. Johnston, Assistant Ofrector Materials, Chemical & Environmental Technology Division of Engineering FROM:

Victor Beneroya, Chief Chemical Engineering Branch 1

Division of Engineering

SUBJECT:

TML-1 TMIRD PARTY REVIEW MEETING SUMERY On April 13, 1983, at Persippany, New Jersey, I attended the fifth third party review ameting on TMI-1 steen generators. The following is a summary of the Cammittee discussions:

The Committee found the non destructive. tests acceptable, and had minor recommendations en the startup and lampaction W T a.

The Committee i

also found the attitional training of personnel adequeta.

Even though the probability of resia flees entering the primary system is leu, the Ceemittes N that an ergenic meterials analyzer he installed.

The Cemeittae aise recommended te lower the acceptable sodium level in the primary coolant to less then 0.1.ppe (from 0.15 ppe).

The Committas was of the spisten that the leek before break analysis is very leportant in the overall program. -They noted that the analysis performed by the licensee og not coetain enou$ conservatism.

MSAC performed an iW analysis. ESAC's results although different, they reach the same conclustee as:.the licemese's that the 0.1 ggia leak would be adegents. Severtheless, because same of the assemptions may have a profound effect en the results, ths Comittee recommended that the licensee perfers a persestric stu$ to eveleste the effect of the assumptions used in the calculattens, te verify that the 0.1 juis leak rate need not be lowered.

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The Committee also stated that monitoring the steam ejectors for radio-activity for leak detection during coeldsun umula not be acceptable, because for the monitoring to be effective, the system should be at equilibrium. During coeldsun, the system is not at equilibrium.

i Secause adateate information uns not provided, the Committee was not satisfied with the stress analysis performed for tube failure during cooldown. They recommended that this analysis be performed again

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considering the assumptions delineated by the Committee members.

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2-W. Johnston The Committee's advice was not to desulfurize the primary system, because in their opinion, it is not cost effective.

By eliminating this step, t.he licensee could gain one month in the restart schedule.

There is some' concern on the additional exposures to plant personnel and the unknown conditions that result from the desulfurization process.

Some Committee members would prefer that the licensee closely examine additional areas in the primary system or attached to the primary system for intergranular stress corrosion.

For the time being, the license has decided to proceed with the desulfurization.

At the end of the meeting. I made it clear that we would not issue the Safety Evaluation Report (SER) until the report to be prepared by the Committee is ande available to the IWC.

At present, we are scheduled to issue the SER by Itsy 9, 1983.

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Victor Senaroya, Chief Chemical Engineering Branch Divisten of Engineering cc:

R. Ve11aer J. Stelt J. Van Vliet G. Laines C. IteCrechen f

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