ML17095A620

Forwards Response to Rev 1 to Generic Ltr 92-01 Re Reactor Vessel Structural Integrity,To Enable NRC to Assess Compliance w/10CFR50.60 & 10CFR50.61 & Fracture Toughness & Matl Surveillance Requirements for RCS

ML17095A620
Person / Time
Site:	Salem
Issue date:	06/30/1992
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17095A621	List: ML17095A620 ML18096A805 ML18096A806
References
GL-92-01, GL-92-1, NLR-N92081, NUDOCS 9207070030
Download: ML17095A620 (6)

Text

Hmn t.Ndtoaborytr JUNS 0 H3<NLR N920$2 United States Nuclear Regulatory Commission Document Control Rooa Washington, DC 20555 Gentlemen:

RESPONSE TO GENERIC LETTER 92-02~REVISION 2 REACTOR VESSEL STRUCTURE INTEGRITY~

10CFR50.5i(f)

SALEM CENEBATZNC STATION UNIT NOS~1 AND 2 FACILITY OPERATING LICENSE NPSI DPR 70 AND DPR 75 DOCKET NOS~50 272 AND 50 322 I'eneric Letter 92<<01, Revision 1 requests PSELC to submit information to enable the NRC to assess compliance vith lOCFR50.60 and 10CFRS0.61, and the fracture toughness and material surveillance requirements for the Reactor Coolant Pressure Baundary set forth in 10CFR50, Appendix G and H.The Salem Generating Station.Unit Nos.1 and 2 responses to Generic Letter 92-01, Revision 1 are provided in Attachment l and 2, respectively.

Please do not hesitate to contact us it there are any questions regarding this submittal.

Sincerely, Attachments Affidavit 0 1 t NLR N92081 Th8LC 12 ShLKK VNLT 2 The follo<LnQ information Mae taken from Salem gnlte 1 and 2 Reactor veaeel Meld Data CR Inc., Deelgn Input FLle T01.5 020 November 1985, and MChp 8824, Ntla co.5alem Unit Ho.2 Reactor Ve eel RadLatlon surveillance Program, january 1979.ggggh~c Meld Curve Ll lance Katerlal Meldment made from Lntermedlate ahel1 platee 84712 1 and 84712-2}~~c 132SX~>I Lnde 1092, l,ot Ho.3833~nd LLnde 1092, Lot.Ho.3774 m'dna F10 1.27.DL7.011 5L.29~71 Ko.45.22.015 Tem 100 100-100 50 50<<%0 40 40 40 100 100 100 210 210 210 ther ft<<lbe 4.5 11 6 11 4 35'5 48oS 72 6$AS 71 SOTS 80.5 86 96e5 106 AS 112 111.5 111~5 l shear 2 6 15 18 20 29 52 52 62$9 55 79 100 90 100 98 100 100 Hil~Lateral ta 1 2o5 1 1~5 1'1 27 42 36$0 56 44 62 81 74~5 80 82 8C 8%~5 Tem i t Dro Met hta terformed b Ct NDT<<40 t RTHDT<<20~t VSE 111 ft"lba-1150't for 40 houreeaMSTatmee 18 RDVioion 0

ATTACHHENT 4 (Reference 4)DIABLO CANYON POWER PLANT UNIT I Intermediate Shell Longitudinal Welds 2-442 A, B, and C Lower Shell Longitudinal Welds 3-442 A, B, and C 6223S/85K}}