ML18017B140

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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  Duke Energy icon.png
Issue date: 07/08/1980
From: CHIANGI N J
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 FACIL:50 400 Shear on Har r j s Nuclear Power Pl ant E UrI j t 1 g Carol ina 50-401 Shearon Harris Nuclear Power Plantr Unit 2E Carolina SO-402 Shearon Harris Nuclear Power Plantq Unit 3g Carolina 50-403 Shearon Harris Nuclear Power Plantr Unit 4r Carolina AUTH INANE AUTHOR A F F IL'A T I ON CWI'ANGI<N,J, Carolina Power 8 Light Co.RECIP~NAME RECIPIENT AFFILIATION DOCKET 0 0 1 05000402 05000403

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

'ENCL g SiZE:/TITLE:Construction Deficiency Report (10CFR50~SSE)"'NOTES: 08 23 REV BR 01 F IL RECIPIENT ID COO//NAME ACTION: A/D LICE',NSAG 21 RUSHBROOKEI'I

~20 INTERNAL: AD/RCI/IE OIREHUM FAC, SFY EQUIP QUAL BR16 HYD/GEO BR'2 LIC QUAL BR MPA OELD P COPIES LTiTR ENCl 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME YOUNGBLOOOrB 15 HILSONE JERRY 14 AEOO EDO 8 STAFF 07 FIElD COOR/IE13 ILE'5 MOOREEV~NRC PDR 02 OR ASSESS BR 17 QA BR 10 STANDROS OEV 11 COPIES LTTR ENCL EXTERNAL: ACRS NSIC 24 04 16 1)'PDR 03 TOTAL NUMBER OF COPIES REQUIRED: LTTR 41 ENCL I~N l I ll I E'1 I"'N I'.ff (i~//

FORM 21-1OOM Pile: SH N-2/18 Item 41 CPA.Carolina Power&Light Company 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 till December, 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)cc: Mr.V.Stellc (2)A 800 V 16 0++~Yours very truly, Original Signed By P,4,~01., Engineering 6 Construction Quality Assurance pei'i s/o P$E<<>ttg>~n~u<

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