ML18018B508

Forwards Safety Analysis of Shearon Harris Safety Parameter Display Sys, Per NRC Generic Ltr 82-33, Requirements for Emergency Response Capability & Section 4.2a of NUREG-0737, Suppl 1

ML18018B508
Person / Time
Site:	Harris
Issue date:	12/02/1983
From:	MCDUFFIE M A CAROLINA POWER & LIGHT CO.
To:	DENTON H R Office of Nuclear Reactor Regulation
Shared Package
ML18018B509	List: ML18018B508 ML18018B510
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, LAP-83-484, NUDOCS 8312120244
Download: ML18018B508 (4)

Text

REGULATORY.I RMATION DISTRIBUTION SYS (RIDS)ACCESSION NBR:8312120244 DOC~DATE: 83/12/02 NOTARIZED:

NO FACIL:50 400 Shearon Har ris Nuclear Power Planti Unit 1i-Carolina 05000400 50 401 Shear on Harris Nuclear Power Plant~Unit 2i"Carolina 05000401 AUTH, NAME AUTHOR AFFILIATION MCDUFFIEgMiA, Carolina Power 8 Light Co~RKCIP~NAME RECIPIENT AFFILIATION DKNTON<H~R, Office of Nuc'lear Reactor Regulationg Director SUBJECT!Forwards"Safety Analysis of Shear on Harris Safety Parameter Display Sys<" per NRC Generic Ltr 82 33'.""Requirements for Emergency Response Capability" L Section 4,2a of NURKG 0737'ISTRIBUTION CODE: A003S COPIES RECEIVKDiLTR QENCL f, SIZE]a~TITLE: OR/Licensing Submittal:

Suppl 1 to NUREG 0737(Generic Ltr'82~33)

NOTES'ECIPIENT ID CODE/NAME NRR LB3=BC INTERNAL: IE/DEPER/EPB NRR/DHFS/PSRB NRR/DL/ORB5 NRR/DS I/ICS8 NRR/DS I/RAB ORB5 PAULSONgH RGN2 EXTERNALS LPDR NSIC COPIES LTTR ENCL 7 7 3 1 5 5 1 1 1 1 1 1 1 1 1 1 1=-RECIPIENT ID CODE/NAME NRR/DHFS/HFEB NRR/DL/ORAB NRR/DSI/CPB NRR/DS I/METB REG FILES NRC PDR NTIS COPIES LTTR ENCL 5 5 1 1 1 1 1 1 1 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED@LTTR 34 ENCl 34 I g'>~;,l.l5, l>>th I'"'f'4 6A r fg'lie)q I)f fl!.f<<f f gag")z<<,'>>I f n'l~"lX"~l hc~q')>>'l>>>f q)Ot>>f l l9<<A"'~0)3>>j, f."'If'1 9)l>l f>>>>g f)<>f (>>rl g>>T lT>>a.).>>.l c'>>~;"-"")If.'.>).)0 f gllv>>i'>>'li<<l'l<

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J'3$<ql>j>)X Ir,'lXHNA l)T 3'I~r)XQ>>>l$1,>>>>lg,l<g P gJI-3 gnaw I r r I(I l 8 l');)Hl'l c If" CXQE, Carolina Power&Light Company DEC 03>983-SERIAL: LAP-83-484 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.1 AND 2 DOCKET NOS.50-400 AND 50-401 NRC GENERIC LETTER 82>>33 REQUIREMENTS FOR EMERGENCY RESPONSE CAPABILITY

Dear Mr.Denton:

Carolina Power&,Light Company hereby transmits one original and forty=copies of the Safety Parameter Display System (SPDS)safety analysis.Carolina Power 5 Light Company committed to submit this SPDS safety analysis in a letter dated April 15, 1983.This information is submitted in accordance with section 4.2a of NUREG-0737, Supplement 1.Yours very truly, M.A.McDuffie Senior Vice President Nuclear Generation CT/tda (8207NLU)Enclosures cct Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP)

Mr.J.P.O'Reilly (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP)

Mr.R.P.Gruber (NCUC)Chapel Hill Public Library Wake County Public Library Mr.Wells Eddleman Dr.Phyllis Lotchin Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.0.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)t.83i2i20244 83i202 PDR ADOCY 05000400 F PDR 411 Fayetteville Street o P.O.Box 1551 o Raleigh, N.C.27602 p'L~t'\~ll'J