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| issue date = 07/08/1980
| issue date = 07/08/1980
| title = 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
| title = 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
| author name = CHIANGI N J
| author name = Chiangi N
| author affiliation = CAROLINA POWER & LIGHT CO.
| author affiliation = CAROLINA POWER & LIGHT CO.
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:REGULATORY ORMATION DISTRIBUTION SYS I (RIDS)ACCESSION NBR: 8007160377 OOC~DATE 80/07/08,'OTARIZED!
{{#Wiki_filter:REGULATORY         ORMATION DISTRIBUTION SYS             I (RIDS)
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
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:==
==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.
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
DISTRI8UTION CODE: 80198         COPIES RECEIVED'LTR TITLE: Construction Deficiency Report ENCL      g    SiZE:
'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
(10CFR50 ~ SSE)
~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
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
1 1
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


==Dear Mr.O'Reilly:==
I ~
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).
N l    I ll      I E              '1 I" 'N I'.
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$E<<>ttg>~n~u<<p n>$(n'C y r ,,<<t~,<<t<<tt<<,t>>~<<~D t f>l~t<<It,"">k<<uwS ttk l Q(, tt~l,.~,>t'"<<8'w'<<f"y~,ifF9it>4L',k
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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 Construction Quality Assurance pei'i 800 V 16 0++~                                                                            s   /o
 
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Latest revision as of 19:15, 3 February 2020

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
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 ENCL g SiZE:

(10CFR50 ~ SSE)

/ " '

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

1 1

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

I ~

N l I ll I E '1 I" 'N I'.

ff (i

~/

/

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

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