ML19249E533

Notifies That FSAR Is Sufficiently Complete to Accept for Docketing.List of Questions Necessary to Complete Review Encl

ML19249E533
Person / Time
Site:	Grand Gulf
Issue date:	05/18/1978
From:	Pawlicki S Office of Nuclear Reactor Regulation
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19249E534	List: ML19249E533 ML19249E535
References
NUDOCS 7910010648
Download: ML19249E533 (4)

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Docket !!os. 50-416/417 MS 01-12 I'E!' ORA!! Dull FOR:

J. F. Stolz, Chief Light l'ater Reactors Branch I:o.1 Division of Project "anagment FRO'!:

S. S. Paulicki, Chief itaterials Engineering Dranch i

SUPJECT:

ACCEPTM;CE REVIEll 0F FSfJt FOR G9A!:0 CULF HUCLEAR STATIO:1, U!!IT 1:0S.1 N:D 2 i^

Plant "ane: Grand Gulf fluclear St'ation, Unit ilos.1 and 2 Suppliers: General Electric; Bechtel Licensing Stage: OL Docket Muobers:

50-416/417 Responsible Branch and Project "anager:

LHR 1; C. O. Thonas Reviewer:

S. J. Bhatt Requested Co.mpletion Date: liay 22, 1973 i

Description of Response: Acceptance Reviest Revict Status: Couplete i

I The liaterials Integrity Section of the !!aterials Engineering Branch, Office of I:uclear Reactor Regulation has conducted an acceptance review l

of the FSAR for the subject application.

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Areas of Revieu Sept.1975 FSAR Standard NTE9 Areas of Revievt Sections Review Plan Reviet:ed i

i S.2.3 Reactor coolant pressure !oundary raterials 5.2.3 5.2.4 Inscrvice inspection and testing of RCPB 5.2.4 5.3.1 Reactor vessel naterials S.3.1 5.3.2 Pressure tenperature liuits 5.3.2 10.2.3 Turbine disk integrity 10.2.3 i.

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Recomendation for Docketing The FSAR in the areas of !TfEB (11aterials Integrity Sect.on) review, h ' "f.)

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is considered acceptable for docketing.

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J. F. Stolz i fE h00T~OINT@$$NL i dAlfa ddd j

Assessment of Cc~pleteness c.

The FSAR contains approximtely 90% of the infomation required in l

The the MTEB (thterials Integrity Section) areas of revicu.

additional infennation identified in the attachnent is required for review within five uecks after docketing.

!!c find the infornation subnitted in the FSAR sufficiently complete that an evaluation can be perfomed with h o rounds of questions.

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( s. s. cau.i S. S. Paulicki, Chief l'aterials Engineering Brcnch Division of Systens Safety Office of "uclear Reactor P.egulation P. J. !!attson, DSS cc:

R. S. Boyd, DPM R. A. Itartfield, !!IPC D. G. Eisenhut, 00R D. Crutchfield,iiRR

0. B. Vassallo, DPM J. P. Knight, DSS R. J. Cosnak, DSS S. S. Paulicki, DSS

11. F. Conrad, DSS M. Bolotsky, DSS S. J. Bhatt, DSS i

Distribution:

Docket File (50-416/417) tiRR Reading File MTEB Reading File RE 1.1-1 l-

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121 1 121.0 MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTION 121.1 You state that the surveillance program will comply with (5.3.1.6)

Appendix H to 10 CFR Part 50. However, any deviations from the requirement: ef American Society for Testing Materials Specifications (ASTM) E 185-73, " Surveillance Tests on Structural Materials in Nuclear Reactors," should be justified.

The maximum anticipated chance in RT and the resultant 121.2 (5.3.2) pressure-temperature limit curves shdId be estimated according to Reaulatory Guide 1.99, Revision 1 (April 1977).

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S. Hanauer R. Mattson R. Boyd W. Mcdonald C. Miller C. O. Thomas M. Srinivasan T. Ippolito J. Stolz R. Tedesco J. Glynn D. Vassallo F. Rosa J. Knox i

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