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=Text=
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{{#Wiki_filter:REGULATORY OHMATION DISTRIBUTION SY M (RIOS)ACCESSION NBR t 8001070351 DOC~DATE t 79/12/20 NOTAH IZED t NO PACILt50 316 Donald 0~Cook Nuclear Power Plantr Onit Zi Indiana 8 AO I H e NAME AUVHOA AFFILIATION SHACCERiD,V, InGiana L Hichigan Power Co~AEGIP,NA11E"HEtivIENr aFFIilATIDN DOCKET 05000316
{{#Wiki_filter:REGULATORY                     OHMATION DISTRIBUTION SY           M   (RIOS)
ACCESSION NBR t 8001070351                         DOC   ~ DATE t   79/12/20 NOTAH IZED t NO                       DOCKET PACILt50 316 Donald                   0   ~ Cook   Nuclear Power Plantr Onit Zi Indiana                     8   05000316 AO I H e NAME             AUVHOA             AFFILIATION SHACCERiD,V,               InGiana L Hichigan Power                       Co ~
AEGIP,NA11E               "HEtivIENr aFFIilATIDN


==SUBJECT:==
==SUBJECT:==
Q~791219rduring anal ysi s described in IK nonconformance identified in small piping sy discrepancy between piping design L as built being implementedrfollowup rept by 800102 DISTRIBUTION CQDEt A002S COPIES RECEIVEDtLTH i ENCL T I TLE: Incident Hepor t s Bulletin 79 lrli st Caused by condition,Mod o-./ae S I l E t aaeeoaeeeaaee NO>rs~Sees W CuS aC C man VZ w wwww&%%&&olww&gglw
Q~       791219rduring anal ysi nonconformance identified in s described in IK Bulletin small piping sy st Caused by 79    lrli discrepancy               between piping design L as built condition,Mod being implementedrfollowup rept by 800102 DISTRIBUTION CQDEt A002S T I TLE: Incident Hepor t s COPIES RECEIVEDtLTH          i  ENCL  aeo  S I l- E .t aaeeoaeeeaaee
~wlow&wtltwwrwtretoksAAa&w4p&ooww'&%I%11~CIApw&~%t%e&w&&SHOIWAI&loswoowoa&
                                                                                                                /
ACTION: INTERNAL;RKC IP I EN 1'D'CODE/NAME 05 BC OÃ84/0 REG F 09 14 TA/EOO i6 FEB i8 PE,ANT SYS BH 20 AU PLAAT SY8 23 FNGA'BR" 25 PAR SYS BR 27 OPERA L IC BR 29 AOX SYS BH HANAOERgS, STS CROUP LEADR COPIES LTTR ENC 1 2 1 i 1 i 1 1 1 1 1 HECIPIKNr COPIES ID CODE/NAME L'rTA ENCL 02 NRC PDR 1 11 MPA 3 15 NOVAK/KNIEL 1 i7 AD FUR ENGR 1 i9 IKC SYS BH HERC SAFf BR i 2q KREI'ER 26 AD/SITE ANAL 1 i 28 ACDENT AALY8 1 E JORDAN/16 IRELAND 3 TM1~H STREET EXTERNALt 03 LPOR 29 ACRS OQ NSIC I S)980 TOTAL NUMBER OF COPIES REQUIRED: LTrR ENCL I I C t II I II,'I N N h Ill I hh 11, yet~INDIA NA&NICIIIGA N PD VER CONPA N Y DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 December 20, 1979 Mr.J.G.Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No.50-316
NO>rs   ~   Sees       W   CuS w wwww&%%&&olww&gglw                 aC C        man          VZ
                                              ~wlow&wtltwwrwtretoksAAa&w4p&ooww'&%I%11~CIApw&~%t%e&w&&SHOIWAI&loswoowoa&
I RKC IP EN                       COPIES                  HECIPIKNr            COPIES 1'D'CODE/NAME LTTR ENC              ID CODE/NAME          L'rTA ENCL ACTION:        05 BC     OÃ84/
INTERNAL;      0   REG   F                           1               02 NRC PDR               1 09                                    2                11 MPA                   3 14 TA/EOO                              1                15 NOVAK/KNIEL           1 i6 FEB                                  i                i7 AD FUR ENGR           1 i8  PE,ANT SYS BH                      1                i9 IKC SYS BH 20  AU PLAAT SY8                      i                    HERC SAFf BR         i 23  FNGA 'BR"                          1                2q KREI'ER 25  PAR SYS BR                          1                26 AD/SITE ANAL           1           i 27  OPERA L IC BR                      1                28 ACDENT AALY8           1 29  AOX SYS BH                                          E JORDAN/16 HANAOERgS,                              1                  IRELAND               3 STS CROUP LEADR                        1                TM1~H STREET EXTERNALt 03 LPOR                                                       OQ  NSIC 29 ACRS I S   )980 TOTAL NUMBER OF COPIES                       REQUIRED: LTrR                 ENCL


==Dear Mr.Keppler:==
I  I C
This is to confirm our verbal report to NRC Region III Inspector, Mr.R.E.Masse, at 1620 hours on December 19, 1979.At that time we reported that as part of the inspection and analysis process mandated by IE Bulletin 79-14, a significant non-conformance was identified in a small piping system of Unit 2 of the Cook Plant.This significant non-conformance arose because of a discrepancy between the piping design analysis and the"as-built" condition.
t II I
The piping involved is a 1.0" diameter line, connected between the primary piping and the excess let-down heat exchanger.
II,'
Reanalysis indicated that the 1.0" diameter pipe would be stressed above the yield limit in the unlikely event that the Design Basis Earthquake occurs.The piping system was reanalyzed with two additional restraints and all the stresses were found to be within the code allowable limit.The modification is being imple-mented in the Unit.A followup report will be submitted by January 2, 1980, as required by Technical Specification Section 6.9.1.8.Sincerely, D.V.Shaller Plant Manager/bab 0,-2,6)s~e cc: J.E.Dolan R.S.Hunter R.W.Jurgensen R.F.Kroeger R.Kilburn R.E.Masse RO:III R.C.Callen MPSC G.Charnoff, Esq.G.Olson J.M.Hennigan PNSRC J.F.Stietzel E.L.Townley Dir., IE (40 copies)Dir., MIPC (4 copies)80010ga L P}}
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hh 11,
 
yet~  INDIANA & NICIIIGAN PD VER CONPA N Y DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 December 20, 1979 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region    III 799  Roosevelt Road Glen  Ellyn, IL      60137 Operating License  DPR-74 Docket No. 50-316
 
==Dear Mr. Keppler:==
 
This is to confirm our verbal report to NRC Region           III Inspector, Mr. R.E. Masse,     at 1620 hours on December 19, 1979.
At that time we reported that as part of the inspection and analysis process mandated by IE Bulletin 79-14, a significant non-conformance was identified in a small piping system of Unit 2 of the Cook Plant.
This significant non-conformance arose because of a discrepancy between the piping design analysis and the "as-built" condition. The piping involved is a 1.0" diameter line, connected between the primary piping and the excess let-down heat exchanger.           Reanalysis indicated that the 1.0" diameter pipe would be stressed above the yield limit in the unlikely event that the Design Basis Earthquake occurs. The piping system was reanalyzed with two additional restraints and all the stresses were found to be within the code allowable limit. The modification is being imple-mented in the Unit.
A followup report will be submitted by January 2, 1980, as required by Technical Specification Section 6.9.1.8.
Sincerely, D.V. Shaller Plant Manager
            /bab cc:   J.E. Dolan                             G. Olson R.S. Hunter                           J.M. Hennigan R.W. Jurgensen                         PNSRC R.F. Kroeger                           J.F. Stietzel R. Kilburn                           E.L. Townley R.E. Masse RO:III                     Dir., IE (40 copies)
R.C. Callen MPSC                      Dir., MIPC (4 copies) 0,-2,6 )s~e      G. Charnoff, Esq.
80010ga
 
L P}}

Latest revision as of 05:27, 29 October 2019

Ro:On 791219,during Analysis Described in IE Bulletin 79-14, Nonconformance Identified in Small Piping Sys.Caused by Discrepancy Between Piping Design & as-built Condition.Mod Being Implemented.Followup Rept Will Be Submitted by 800102
ML17326A452
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 12/20/1979
From: Shaller D
INDIANA MICHIGAN POWER CO.
To:
References
IEB-79-14, NUDOCS 8001070351
Download: ML17326A452 (4)


Text

REGULATORY OHMATION DISTRIBUTION SY M (RIOS)

ACCESSION NBR t 8001070351 DOC ~ DATE t 79/12/20 NOTAH IZED t NO DOCKET PACILt50 316 Donald 0 ~ Cook Nuclear Power Plantr Onit Zi Indiana 8 05000316 AO I H e NAME AUVHOA AFFILIATION SHACCERiD,V, InGiana L Hichigan Power Co ~

AEGIP,NA11E "HEtivIENr aFFIilATIDN

SUBJECT:

Q~ 791219rduring anal ysi nonconformance identified in s described in IK Bulletin small piping sy st Caused by 79 lrli discrepancy between piping design L as built condition,Mod being implementedrfollowup rept by 800102 DISTRIBUTION CQDEt A002S T I TLE: Incident Hepor t s COPIES RECEIVEDtLTH i ENCL aeo S I l- E .t aaeeoaeeeaaee

/

NO>rs ~ Sees W CuS w wwww&%%&&olww&gglw aC C man VZ

~wlow&wtltwwrwtretoksAAa&w4p&ooww'&%I%11~CIApw&~%t%e&w&&SHOIWAI&loswoowoa&

I RKC IP EN COPIES HECIPIKNr COPIES 1'D'CODE/NAME LTTR ENC ID CODE/NAME L'rTA ENCL ACTION: 05 BC OÃ84/

INTERNAL; 0 REG F 1 02 NRC PDR 1 09 2 11 MPA 3 14 TA/EOO 1 15 NOVAK/KNIEL 1 i6 FEB i i7 AD FUR ENGR 1 i8 PE,ANT SYS BH 1 i9 IKC SYS BH 20 AU PLAAT SY8 i HERC SAFf BR i 23 FNGA 'BR" 1 2q KREI'ER 25 PAR SYS BR 1 26 AD/SITE ANAL 1 i 27 OPERA L IC BR 1 28 ACDENT AALY8 1 29 AOX SYS BH E JORDAN/16 HANAOERgS, 1 IRELAND 3 STS CROUP LEADR 1 TM1~H STREET EXTERNALt 03 LPOR OQ NSIC 29 ACRS I S )980 TOTAL NUMBER OF COPIES REQUIRED: LTrR ENCL

I I C

t II I

II,'

I N

N h

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hh 11,

yet~ INDIANA & NICIIIGAN PD VER CONPA N Y DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 December 20, 1979 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

This is to confirm our verbal report to NRC Region III Inspector, Mr. R.E. Masse, at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> on December 19, 1979.

At that time we reported that as part of the inspection and analysis process mandated by IE Bulletin 79-14, a significant non-conformance was identified in a small piping system of Unit 2 of the Cook Plant.

This significant non-conformance arose because of a discrepancy between the piping design analysis and the "as-built" condition. The piping involved is a 1.0" diameter line, connected between the primary piping and the excess let-down heat exchanger. Reanalysis indicated that the 1.0" diameter pipe would be stressed above the yield limit in the unlikely event that the Design Basis Earthquake occurs. The piping system was reanalyzed with two additional restraints and all the stresses were found to be within the code allowable limit. The modification is being imple-mented in the Unit.

A followup report will be submitted by January 2, 1980, as required by Technical Specification Section 6.9.1.8.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan G. Olson R.S. Hunter J.M. Hennigan R.W. Jurgensen PNSRC R.F. Kroeger J.F. Stietzel R. Kilburn E.L. Townley R.E. Masse RO:III Dir., IE (40 copies)

R.C. Callen MPSC Dir., MIPC (4 copies) 0,-2,6 )s~e G. Charnoff, Esq.

80010ga

L P