ML20148F781

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Requests Util to Revise Proposed Tech Specs Re Steam Generator Tube Surveillance Per Jul 1975 Revision 1 of Reg Guide 1.83.Model Tech Specs Re Steam Generator Inservice Insp Encl
ML20148F781
Person / Time
Site: Yankee Rowe
Issue date: 09/10/1976
From: Schwencer A
Office of Nuclear Reactor Regulation
To: Groce R
YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML20148F784 List:
References
NUDOCS 8011060731
Download: ML20148F781 (3)


Text

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t SEP 101976

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Yankee Atomic' Electric Company i

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t 30 and 32 of Appendix A to 10 CFR Part 50 require ;theticomponents that are part of the reactor coolar.t pressure boundary receive periodic inspection and testing of c,ritical areas to

assess:their structural;and leaktight:integetty. LThe steam generator f

tubes constitete'ever 50% of, the area :of the total ~ primary system

. pressure-retaining boundary in pressu~rized-water reactors. Our letter dated ~

' July 18,1974;' requested you to propose suitable' technical specifications for the serve 111ance of the' steam' generator tubes consistent with the

., requirements of the GDC and. Regulatory Guide 1.83 titled " Inservice In-1 fspection of Pressurized Water Reactor Stean Generator Tubes." Since your

' proposal was submitted,'R.G.1.83 has1been revised; therefore, we request that you revise your submittal to.be consistent with the enclosed model t

technical specf fications.which are based on Revision.1 'of R.G.1.83, dated July 19756. ~ N ; >'

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Both' the Loriginal ande ing limit rer)se and plugging criteria.ibut neitherlprovides guidance on how'these are to i be quantifled.? LThe, plugging, limit in)theLenclosed ~model technical specifi-f~

Lcations is based,an the minimum tube wellithickness'needed to maintain 4

tube integrity duringfa;LOCA combined.with a safe shutdown earthquake and

'an operational' allowance to account forJ time intervals between inspections.

i We have concluded that plugging limits.that are based on these considerations '

. : satisfy the requirements of the GDC and. are acceptable.to us.

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%. fore,'3enerator tubedeakageLcan,b' s Steam e an indication ofitube degradation; there-

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operation should be included (leakage limit and'allimiting condition for :

we, have" concluded that a i

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the technical-specif1 cations;to ensure timely *

. action lin therevent of steam generator. tube, degradation. A leakage limit

.f ito us.y~M.one in thelenclosed modell: technical: specifications'is a i

such as the

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Certain steam generators have completed the first cycle of operation l

1 with tube inspection results that have indicated little discern-ible degradation. - These early-in-life inspection results may not be indicative of the total 40 year design life of steam generator tubes in terms of tube integrity. Therefore, we have concluded.that sur-l veillance of steam generator. tube integrity should be covered by technical t

specifications for all facilities including those where early inspection cycles have not indicated any discernible or increasing degradation.

I e The enclosed model technical specifications gives credit for favorable i

early.: inspection _results by; extending subsequent. inspection intervals

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resubeit your request for a'licen;se' amendment using the enclosed model i

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, technica1Lspecifications.for guidance. The model. technical. specifications i

. Lshould be' appropriately; adapted :tolyour spectfic' format and to the number

.of steam, generators 14 your plant.'

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s Yankee Atomic Electric Company September 10, 1976 cc: Mr. Donald G. Allen, President Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Public Library 402 Main Street Greenfield, Massachusetts 01581 i

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