ML19317G743

Advises That Encl NRC 771209 Request for Completion of Questionnaire Re Steam Generator Operating History Is Appropriate Per Gao Blanket Clearance.Addressed to All PWR Licensees

ML19317G743
Person / Time
Site:	Indian Point, Arkansas Nuclear, Rancho Seco
Issue date:	02/10/1978
From:	Goller K Office of Nuclear Reactor Regulation
To:	ARKANSAS POWER & LIGHT CO., CONSOLIDATED EDISON CO. OF NEW YORK, INC., SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML19317G744	List: ML19317G743 ML19317G761
References
GL-78-4, NUDOCS 8004010573
Download: ML19317G743 (2)

Text

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UNITED STATES f

,7 NUCLEAR REGULATORY COMMISSION

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.I WASHINGT ON, D. C. 20515 February 10, 1978 S

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TM-To All PWR Facility Licensees E

Gentlemen:

7 By letter dated December 9,1977, copy enclosed, we requested you and all other PWR facility licensees to complete and submit a p

questionnaire on steam generator operating history that was enclosed.

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The letter stated that the request for infomation was approved by

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GA0.under a blanket clearance.

Questh ns have been raised about the appropriateness of this request for infonnation in light of the Federal Reports Act and about the referenced GA0 blanket cl earance. These questions have been discussed with representatives of GA0 and it was detemined that this clarifying letter should be i

sent to each recipient of our original letter.

GA0 has agreed that this request properly fits under the GA0 blanket clearance for reports concerning possible generic problems and the applicable GA0 clearance number should have been R0072 rather than R0071.

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The request for additional information was prompted by the continuing degradation of tubes in all three vendors' steam generators.

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degradation is an important safety concern of the NRC because such tubes form part of the primary coolant pressure Foundary. Several k;j ="

forms of degradation that have been observed in steam generators in

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recent months have included the wastage of tubes at Palisades and t=

other facilities, stress corrosion at Ginna and other facilities, vibration cracking and " dinging" of tubes at the Oconee (B&W) facilities, antivibration bar fretting at San Onofre, and " denting" of tubes ar.'i associated support plate "hourglassing" and cracking at Surry, Turkey Point and about 15 other CE and W facilities.

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These even% have resulted in many shutdowns of niiclear power p

stations aad the safety significance of certain of these events L

have prompted the NRC to issue safety Orders.

It is this need

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for important safety information that has dictated this request

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for additional information.

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All PWR Facility Licensees February 10, 1978

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Our previous letter a,cknowledged that selected portions of the information being requested may already be available to the NRC, but not in a convenient format which is readily accessible. We l= ===

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therefore requested that you assist us by returning a single completed copy of the enclosed questionnaire. We would like to

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F clarify that an acceptable response to any item in the questionnaire E=EER would be to provide specific reference to any information previously submitted to the NRC, by an original response, or any combination thereof, whichever and for whatever reasons you elect to use.

Our previous letter further requested that you submit any changes or additions to your initial submittal to reflect the future

' operating experience with your steam generators. This would enabla us to maintain the information current, which, as we stated, we will

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periodically publish and send copies to all participants. As we indicated, this would enable the NRC, you and others to draw from the operating experience of the entire nuclear industry on an 1.....

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ongoing basis when making safety and other decisions concerning steam generators in PWR plants. We are planning to prepare a s.

submission to GA0 for clearance of a request for reporting a

information regarding changes or additions to your initial

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submittal ~under~ this request.

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We hope that the need for this clarification caused you no inconvenience.

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Because of the problems discussed above, we are extending the date c.

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for submitting the requested information to March 1,1978.

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1 Karl R. Goller, Assistant Director 5

for Operating Reactors Division of Operating Reactors Q_

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Enclosures:

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Letter dtd. 12/9/77 to PWR Licensees r.gg 2.

Questionnaire x

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