L-78-195, Information Regarding Fracture Toughness and Potential for Lamellar Tearing of Steam Generator and Reactor Coolant Pump Support Materials Was Turned Over to NRC Staff

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Information Regarding Fracture Toughness and Potential for Lamellar Tearing of Steam Generator and Reactor Coolant Pump Support Materials Was Turned Over to NRC Staff
ML18114A169
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/05/1978
From: Robert E. Uhrig
Florida Power & Light Co
To: Reid R
Office of Nuclear Reactor Regulation
References
L-78-195
Download: ML18114A169 (3)


Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)

'DISTRIBUTION FOR INCOMING MATERIAL 50 3&5 REC: REID R W ORG'HRIG R E DOCDATE: 06/05/78 NRC Fl PWR 5 LIGHT DATE" RCVD: (>6/13/7 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 3 ENCL 0 ADVISING NRC REQUEST OF 09/14/77 FOR INFO CONCERNING FRACTURE TOUGHNESS AND THE POTENTIAL FOR LAMELLAR TEARING IN THE STEAM GENERATOR AND REACTOR COOLANT PUI"1P SUPPORT MATERTALMFOR UNIT ir WAS TURNED OVER DURING A MEETING HELD ON MAY iii 1978 IN NRC OFFIQC5 PLANT NAME: ST LUCIE Si REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:

++~++++++++++++~+ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS FRACTURE TOUGHNESS 5 POTENTIAL FOR LAMELLAR TEARING.

<DISTRIBUTION CODE A018)

J FOR ACTION: BR CHIFF ORBN4 BC4+LTR ONLY<5)

INTERNAL: LTR ONLY< 1) NRC PDR++LTR ONLY<i)

I 5 E4HILTR ONLY(2) OELD++LTR ONLY(i>

HAlVAUER++LTR ONLY < 1 ) AD FOR OPER TECH<<LTR ONLY<i)

ENGIIVEERING BR++LTR ONLY(1 > REACTOR SAFETY BR~~LTR ONLY('1>

PLANT SYSTEMS BR++LTR ONLY< 1) EEB++LTR Oh!LY < 1 )

EFFLUENT TREAT SYS~+LTR ONLY(i> R SNAIDER+4LTR ONLY(i >

H. LEV IIV+4~LTR ONLY < 2) II'g A

S. PA WLICK I +4LTR ONLY < 1 )

EXTERNAL: I PDR S FT PIERCE) FL4~LTR ONLY(i >

TIC4~<~LTR ONLY< 1)

NS I C4H~LTR ONLY ( 1 >

ACRS CAT B414LTR ONLY< 16)

DISTRIBUTION: LTR 40 ENCL 0 CONTROL NBR: 781640026'R.

SIZE: ip +

END 4 %%%%%4%4%4 4 %4%4% %%%%%%%%%%%

II S NUCLEAR REGULATORY COHhtlISSIOM C DAILY ACCESSIOM LIST 05/11/78 PAGE 58 FIL= LOCATION 7346-0259 TASK MBR-EHO FICHE: MBR P NOTARIZED - NO LPDR- MO CLASS=

H REC> AFFILIATIOM- NRC ORG A. FIL IATION= NRC OF SITE AGENDA FOR THE SUB JECT FA CILITY~

8129-0009 TASK MBR:

ETTER, .. FICHE MBR P+1P NOTARIZED = NO LPDiR- YES CLASS -

RECP AFF ILIATION= NRC PRG AFFILIATION: DAIRYLAND PMR COOP IMG ENDORSEMENT MO 28 FOR MUC ENERGY. LIABILITYPOLICY NO MF-217 ~

lT" ft2 7333-0090 TASK N8R.

EHO FICHE MBR P NOTARIZED: 'O LPDR: MO CLASS-RECP AFFILIATION NRC ORG AFFIL IATIOM- NRC SISTAhlCE REQUEST TO EVAN UATE APPLICAhlT~ 5 REQUEST TO APPLY ASHE CODE CASE TO THE BOLTING h'lATERILAS USED IM THE CONCRETE ANCHORS FOR EQUIPMENT ED AT THE SUB JECT FACILITY

KEMMFKIND,;... ~

FLORIOA POWER 8( LIGHT COMPANY, June 5, 1978 L-78-195 Office of Nuclear. Reactor Regulation Attention: Mr. R. W. Reid, Director Operating Reactors Branch 54 l~

- U. S.

Division of Operating Reactors Nuclear~:Regulatory Commission 4~ i ggp Washington, D. C. 20555 @/~+Op~(

Dear Mr. Reid:

8 Re: St. Lucie Unit 1 E..-

Docket No. 50-335 Fracture Toughness and -Potential For Lamellar Tearing of Steam Generator and Reactor Coolant Pump Support Materials On September,14, 1977, in a letter from Mr. Don K. Davis, the NRC requested that Florida Power.a'ight Company prove.'de information concerning fracture toughness and the potential for lamellar tear-ing in. the steam generator and reactor coolant pump support materials for St. Lucie Unit l.

Please be advised that this information was turned over to NRC staff reviewers during a meeting in your offices on May ll, 1978.

Very truly yours, Robert E. Uhrig Vice President REU/MAS/mb cc: Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire 781640026 Iws/~

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