ML20210T169

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Forwards Matls Engineering Branch Request for Addl Info Re PSAR Through Amend 8 in Order to Complete Evaluation. Response Requested by 750328 in Order to Maintain Current Schedule
ML20210T169
Person / Time
Site: Satsop
Issue date: 01/27/1975
From: Maccary R
Office of Nuclear Reactor Regulation
To: Deyoung R
Office of Nuclear Reactor Regulation
References
CON-WNP-1745 NUDOCS 8605290781
Download: ML20210T169 (2)


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' Docket Nuisheris:

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Responsible Branch and Projest. Manager: DiR 1-3; l

Requested Cospletiin Dates. January 24, 1975 l

l Description of Response Second Round, Regulatory Scaff Positions (0-2)-

l Review status

-Applicant Response Required l

Information submitted by the applicant in the PSAR,. threagh /mpadmoot 3,1, I

has been reviewed by the Materials. Applications section, Materials l

Engineering Branch. Office of Nualear Reactor Regulation., Adequate

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'responsea'to the~ enclosed Regulatory staff positions are requited before l

we can complete our evaluation. In order to maintain the current sched-i

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120.0 MATERIALS ENGINEERING BRANCH, APPLICATIONS SECTION l

120.23 (RSP)

The response to Item 120.6 in. Amendment 5 regarding avoiding (10.5) oignificatte sensitikatica of austenitic stainless steel com-(10.4) ponents refers only to the ESF components, whereae Itaa 120.6

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pertains to the steam and feedwater materials also. The response is acceptablo for the 'EST ccmpen9nts. Confirm that sioilar st9ps, -in accordance with the recohmandations o2 Ret;u-latory Guida l A4, will be taken to avaid significant ser.ci-tizatt.on of pressure-retctining austenitic stcinless steel components of thi. steam and feedwater sys ums.

120.24 (RSP)

The rasponse to Iten 120.16 in Amendment 5 regsrding confor-(6.1) mance to the interim Regulatory p.osition on R2gulatory Guide (10.3) 1.31 is acceptable except foT par.agraphs 4)b) ;tnd 4)c) dec-c (10.4) cribing a test sample to represent the productior. weld when a production weld must be evaluated for accept 0ility. This test eat:ple is not permitted. The -interin a).terinte Regit-

-latory position 4.b. states:

"When.the production uald is below the teinimte acepetable level of delta ferrite, a sample i

of thn wold shall be removed, and a metal 3cSrcphi;. c.:.cai.mti-or a bend test shall be mde on a trannverse.<:ection to deters-mine the presence or absence of excessive fissures......,.."

Confirm that if Regulatory position 4.b. is followed as an alternate, the testing will be of the production Velds, i

120.2S (RSP)

The r.esponse to item 120.16 itt Am6u.dcent 3 is s:nacceptable.

The Regulatory position is that the fracture couganess pro-i perties of the pressure-retaining ferr101e'matarfalg of all l

Class 2 and 3 components in WPPSS Nuclear Projec' e No. 3 and 5 must meet the requirements of st:bsubarticles NO-2310 afd ND-2310

  • of the Stimmer 1972 Addenda to Section IQ of the ASNd Code. The

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?egulittory pcsition requireaents for fracture toughness pro-perties of Class 2 and 3 ferritic catarial components :.re inte.nded to supplenent thosa of the 15i74 7dition of Section III of the f.SME Code.

Confir:n that you will comply with this ReguAatory position.

120.26 (RSP)

The response to Item 120.15 in Amendment 5 is r.o;; clear.

The Reg ~atory pcuition is titat the Icechanicc1 properties of mat.erials speci'fied lor use in a,11 Class 2 and Class 1 component.s df WPPSS Nuc14ac Projects No. 3.aAd 5 bust be either or state-j j.n Appendits I to Section III of the Code, or alternately, a:s indic;.ited in Par ts A, B, 'and C of 3cciion II of the Ccde. Confirm that you will comply aith rhis Regyletery posttica.

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