ML18017B140

Interim Deficiency Rept Re Significant Failure of Reactor Protection Sys Following Main Feedline Break.Westinghouse Has Indicated Corrective Action Cannot Be Completed Before Dec 1981.Final Rept Will Be Issued Upon Completion

ML18017B140
Person / Time
Site:	Harris
Issue date:	07/08/1980
From:	Chiangi N CAROLINA POWER & LIGHT CO.
To:
References
SH-N-2-18, NUDOCS 8007160377
Download: ML18017B140 (4)

Text

REGULATORY ORMATION DISTRIBUTION SYS I (RIDS)

ACCESSION NBR: 8007160377 OOC ~ DATE 80/07/08,'OTARIZED! NO DOCKET FACIL:50 400 Shear on Har r j s Nuclear Power Pl ant E UrI j t 1 g Carol ina 0 50-401 Shearon Harris Nuclear Power Plantr Unit 2E Carolina 0 1 SO-402 Shearon Harris Nuclear Power Plantq Unit 3g Carolina 05000402 50-403 Shearon Harris Nuclear Power Plantr Unit 4r Carolina 05000403 AUTH INANE AUTHOR AF F IL' AT I ON CWI'ANGI<N,J, Carolina Power 8 Light Co.

RECIP ~ NAME RECIPIENT AFFILIATION

SUBJECT:

Interim deficiency rept re significant failure of reactor protection sys following main feedline break.Hestjnghouse has indicated corrective action cannot be completed befo,re Dec 1981.Final rept will be issued upon completion.

DISTRI8UTION CODE: 80198 COPIES RECEIVED'LTR TITLE: Construction Deficiency Report

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ENCL g SiZE:

(10CFR50 ~ SSE)

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NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID COO//NAME LTiTR ENCl ID CODE/NAME LTTR ENCL ACTION: A/D LICE',NSAG 21 YOUNGBLOOOrB 15 RUSHBROOKEI'I ~ 20 HILSONE JERRY 14 INTERNAL: AD/RCI/IE 1 AEOO

'2 OIREHUM FAC, SFY EQUIP QUAL BR16 HYD/GEO BR LIC QUAL BR 1

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ILE'5 EDO 8 STAFF FIElD COOR/IE13 MOOREEV ~

07 MPA 08 1 NRC PDR 02 OELD 23 1 OR ASSESS BR 17 P REV BR 1 QA BR 10 F IL 01 1 STANDROS OEV 11 EXTERNAL: ACRS NSIC 24 04 16 1)'PDR 03 TOTAL NUMBER OF COPIES REQUIRED: LTTR 41 ENCL

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FORM 21-1OOM Pile: SH N-2/18 CPA.

Carolina Power & Light Company Item 41 Raleigh, N. C. 27602 July 8, 1980 Mr. James P. O'Reilly United States Nuclear Regulatory Comad.ssion Region XI 101 Marietta Street, NQ Atlanta, Georgia'0303 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS ~ 1, 2f 3f AND 4 DOCKET NOS. 50-400, 50-401, 50-402, 50-403 POTENTIALLY SIGNIFICANT PAILURE OP THE REACTOR PROTECTXON SYSTEM POLLOWING A MAIN PEEDLXNE BREAK INTERIM REPORT

Dear Mr. O'Reilly:

The following was discussed with and concurred by your Mr. J. Bryant on July 7, 1980:

(a) The potentially significant failure of the reactor protection system following a main feedline break is considered reportable pex the provisions of 10CFR50.55(e). Such a break within containment could result in the heatup of the steam generator level measurement refer-ence resulting in delaying protection signals.

(b) Westinghouse has indicated that due to operating plants receiving priority over plants under construct:ion, corrective action on this item for the Shearon Harris Nuclear Power Plant units cannot be completed tillDecember, 1981.

(c) Upon completion of the corrective action, the final 10CPR50.55(e) report will be submitted.

(d) Westinghouse has already reported this item per the provisions of 10CFRf Part 21.

If you have any questions regarding this matter, please do not hesitate to contact me.

KVH/gea (909741) Yours very truly, cc: Mr. V. Stellc (2) A Original Signed By P,4,~01 Engineering 6

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Construction Quality Assurance pei'i 800 V 16 0++~ s /o

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