ML20052D001

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Discusses Comments in to H Denton Re Steam Generator Eddy Current Insp Interval for Facility
ML20052D001
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 04/19/1982
From: Novak T
Office of Nuclear Reactor Regulation
To: Patricia Anderson
WISCONSIN'S ENVIRONMENTAL DECADE
References
TAC-48122, NUDOCS 8205060187
Download: ML20052D001 (2)


Text

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y, Mr. Peter Anderson 97 g[

Wisconsin's Environmental Decade 2

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Dear Mr. Anderson:

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/M' We have received your comments regarding the steam generator eddy a inspection interval for Point Beach Nuclear Plant Unit 1, as contained -

in your March 12, 1982 letter to Mr. H. R. Denton, Director of Nuclear Reactor Regulation.

The staff has not yet completed its evaluation of the information presented to us by Wisconsin Electric Power Company (licensee) during the January 27, 1982 meeting with the licensee; however, you may be interested in learnfrG that the licensee has performed a shutdown of Point Beach Nuclear Plant Unit 1 on March 27, in order to conduct a steam generator eddy current inspection.

The purpose of the inspection is to ensure that the operability of Unit I would not be affected by steam generator leakage during the upcoming Unit 2 annual refueling outage. The staff will provide you with a copy of our eval-uation of the proposed full cycle operating interval when completed.

We take exception with your statement that " permitting operation with frequent inspections (i.e. 90 to 180 effective full power day intervals) by itself creates totally unacceptable risk..." The Technical Specifications requirements con-cerning restrictive steam generator tube leakage limits coupled with tube plugging limits and frequent steam generator tube inservice inspections provide reasonable assurance that the public health and safety will not be endangered.

Further your letter states that "...the Ginna episode impels the necessity to require an immediate shutdown and inspection at Point Beach..."

The staff is continuing its evaluation of the Ginna incident and has not yet deter-mined what additional requirements, if any, it may place on licensees' of pressurized water reactors as a result of its findings. Since the tube rupture at Ginna appears to have been caused by the presence of foreign objects in the secondary side of the steam generator, it appears that this has little direct relevancy to the discussion of the frequency of eddy current inspections as is implied by your letter.

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2-We do appreciate your comments and will bear them in mind while we continue our evaluation.

Sincerely.

Originni GiE"Od DY3 n.ccaa M.11ovak Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing cc: See next page DISTRIBUTION cAccket File Local PDR ORB Rdg D.Eisenhut JHeltemes RAClark PKreutzer-C OELD NSIC I&E (1)

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