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AlI A!)id Ib A r' PHI /1 P6'dNi rKU i ]t i AlL Ull1 - HUJ1 m t/W                         l m       .
AlI A!)id Ib A r' PHI /1 P6'dNi rKU i ]t i AlL Ull1 - HUJ1 m t/W m
    .        PE,T 21 IIBUIFICATIO$ NO. 9/           M'"#                 C0'PANY tRE_       W A' DATE 0~ LETTtR.           3/77I/         ID2(ET NO.       f6 4 2 f
PE,T 21 IIBUIFICATIO$ NO. 9/
                                        /                                           /
M'"#
C0'PANY tRE_
W A' DATE 0~ LETTtR.
3/77I/
ID2(ET NO.
f6 4 2 f
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D - DISTRIBUTED ORIGINLL EPORTf SLP?LEnTARi DISTRIBUTION:
D - DISTRIBUTED ORIGINLL EPORTf SLP?LEnTARi DISTRIBUTION:
PEACTOR @                           FLEL CYCLE &                   SAFEGt1ARDS (S)
PEACTOR @
IE FILES                           [ABIALS @                        IE FILES EES O M                             IE FILES                       AD/SG AD/FFFSI                         AD/ROI PEGIO'E I,II,III,IV,V               EGIONS I,II,III,IV,V           EGIONS 1.,II,III.,IV,V VSO3R BR. R-IV                     \dOJR BR. R-IV                   VSOJR BR. PcIV LT3 / t'PA FIG 5715                 I?SS/FD'S       SS-595         pg/93L AE03     .      FIG 7502           LOEB/FPA       l;iG 5715         g.33 / gg 33_ggi Cect;nnw m m 7zn N                                   A53D           MG 7602           LO 3 / FP"^   FIG 5715 OtcolT;s mes 7zn NR?/DSI                             ASLBP E/d     450               AEOD         FIG 7E02 tiDFDST                         -                                    Cifadtmw mnB'7zr SA3/SP t-iB-7210A               ASLEP     E/W 450 NRP/DJL               -
FLEL CYCLE &
CEhTR5 L FILES     016         CEhTRAL FILES     016 ASL3'o     E/d USD CSHRAL FILES ( GRD:0           CSURat FILES     (CHRJ'O C5ii?A1. FILES       016             PDR                             CBERAL FILES     SS-395 CSERAL FILES         (GR0fD           LPDR                   %      PDR
SAFEGt1ARDS (S)
                                          ~                   gr, PDR                                   TERA '                     e,   LPDR a   9               .-
IE FILES
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[ABIALS IE FILES EES O M IE FILES AD/SG AD/FFFSI AD/ROI PEGIO'E I,II,III,IV,V EGIONS I,II,III,IV,V EGIONS 1.,II,III.,IV,V VSO3R BR. R-IV
                                                                            ~7 W
\\dOJR BR. R-IV VSOJR BR. PcIV LT3 / t'PA FIG 5715 I?SS/FD'S SS-595 pg/93L AE03 FIG 7502 LOEB/FPA l;iG 5715 g.33 / gg 33_ggi Cect;nnw m m 7zn N
E,N             A     .
A53D MG 7602 LO 3 / FP"^
FIG 5715 OtcolT;s mes 7zn NR?/DSI ASLBP E/d 450 AEOD FIG 7E02 tiDFDST Cifadtmw mnB'7zr SA3/SP t-iB-7210A ASLEP E/W 450 NRP/DJL 5
CEhTR L FILES 016 CEhTRAL FILES 016 ASL3'o E/d USD CSHRAL FILES ( GRD:0 CSURat FILES (CHRJ'O C5ii?A1. FILES 016 PDR CBERAL FILES SS-395 CSERAL FILES (GR0fD LPDR PDR gr,
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ACTION:
ACTION:
                                                          +                               '
+
PRELIMItMRY EVALUATION OF THE' ATTACHED REPORT ITOICATES LEAD R FOLL0hU? AS SFOWN BELOW:
PRELIMItMRY EVALUATION OF THE' ATTACHED REPORT ITOICATES LEAD R FOLL0hU? AS SFOWN BELOW:
IE                                         NRR _                        R.SS ]           cygg {
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            ~
TENNESSEE VALLEY AUTHORITY
TENNESSEE VALLEY AUTHORITY
    ;                                      cH/ TTANOOOA. TENNESSEE 3 hot                 [, g g 3 400 Chestnut Street Tower II l' arch 27, 1981 SQRD-50-328/81-11 N
~
Mr. JamesJ. O'Reilly, Director Office of Inspection and Enforcement U.S. NuclearMegulatory Comission Region II - Sdite 3100 101 Marietta St et Atlanta, Georgia     0303
cH/ TTANOOOA. TENNESSEE 3 hot
[, g g 3 400 Chestnut Street Tower II l' arch 27, 1981 SQRD-50-328/81-11 N
Mr. JamesJ. O'Reilly, Director Office of Inspection and Enforcement U.S. NuclearMegulatory Comission Region II - Sdite 3100 101 Marietta St et Atlanta, Georgia 0303


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==
 
SEQUOYAH !!UCLEAR PUiNT UNIT 2 - STPISS CORROSION CRACKING IN TUBING ON THE PIAC"0B COOLANT PUMP OIL COOLERS - SQRD-50-326/81 FINAL P2 PORT The subject deficiency was initially reported to !!RC-0IE Inspector R. W. Wright on December 2, 1980, in accordance with 10 CFR 50.55(e) as NCR SQH NEB 8028. Interim nports were sub:r.itted on January 2 and
SEQUOYAH !!UCLEAR PUiNT UNIT 2 - STPISS CORROSION CRACKING IN TUBING ON THE PIAC"0B COOLANT PUMP OIL COOLERS - SQRD-50-326/81               FINAL P2 PORT The subject deficiency was initially reported to !!RC-0IE Inspector R. W. Wright on December 2, 1980, in accordance with 10 CFR 50.55(e) as NCR SQH NEB 8028. Interim nports were sub:r.itted on January 2 and
-February 3, 1981. Enclosed is our final report. We consider 10 CFR 21 applicable to this deficiency.
            -February 3, 1981. Enclosed is our final report. We consider 10 CFR 21 applicable to this deficiency.
If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 857-2581.
If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure                                                       -
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure Mr.VictorStello,Jr., Director (Enclosure)i[
cc:  Mr.VictorStello,Jr., Director (Enclosure)i[
cc:
t         Office of Inspection and Enforcement U.S. Nuclear Regulatory Co::: mission Washington, DC 20555 I
t Office of Inspection and Enforcement U.S. Nuclear Regulatory Co::: mission Washington, DC 20555 I
An Equct Or;:ortani*y Emdov v
An Equct Or;:ortani*y Emdov v


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      .*  .4                                                                                             _
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              ^
,I ENCLOSURE
      ,I                                               ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 STRESS CORROSION CRACKING IN T3ING         .
^
ON THE REACTOR COOLANT. PUMP MOTC'R C:L CCOLERS -
SEQUOYAH NUCLEAR PLANT UNIT 2 STRESS CORROSION CRACKING IN T3ING ON THE REACTOR COOLANT. PUMP MOTC'R C:L CCOLERS -
SQED-501328/81-11 10 CFR 50.55(e)
SQED-501328/81-11 10 CFR 50.55(e)
                                                  ' FINAL -REPORT
' FINAL -REPORT Description o
_y Description o         _
_y The 'Sequoyah'unitI1 reactor coolant'pu=p motor. lubricating oil coolers developed excessive tube leakage during the hot functional test due to stress corrosion cracking (SCC) in the tube =aterial. Examination of the tube aterial removed from one such heat exchanger. revealed that the tubes were of admirality brass which has been found to be s.sceptible to stress corrosion cracking in this application. The cracking is due :to the presence of a==enia, which in conjunction with ~
The 'Sequoyah'unitI1 reactor coolant'pu=p motor. lubricating oil coolers developed excessive tube leakage during the hot functional test due to stress corrosion cracking (SCC) in the tube =aterial. Examination of the tube aterial removed from one such heat exchanger. revealed that the tubes were of admirality brass which has been found to be s.sceptible to stress corrosion cracking in this application. The                       ,
cracking is due :to the presence of a==enia, which in conjunction with ~
residual and' operating stresses, causes the stress
residual and' operating stresses, causes the stress
* corrosion cracking.
* corrosion cracking.
* The a :enia present is apparently a product of the deco: position of -
The a :enia present is apparently a product of the deco: position of -
hydrazine frot the co:ponent cooling syster water treatment.
hydrazine frot the co:ponent cooling syster water treatment.
I:plications to S'equoyah unit 2 were investigated, and it was determined that these heat exchanger tubes were also cade :f ad irality brass.              .
I:plications to S'equoyah unit 2 were investigated, and it was determined that these heat exchanger tubes were also cade :f ad irality brass.
Safetv Inclications-Tube leakage'which could have resulted from SCC would al' low water to
Safetv Inclications-Tube leakage'which could have resulted from SCC would al' low water to
(                 mix with the lubricating oil for the reactor coclant pump motor bearings. Water. coring in contact with the bearings?cculd possibly cause thec _to seize. This -could reduce .the pu=ps' coastdown time during a reactor- trip, 'which could adve'rsely affect the safety of.~ the plant.; Continued' forced ' circulation of ' reactor coolant is required in the short ter after reactor trip .to remove the initial decay heat l ead. # Although all four reactor coolant pu=ps 'are not required for-uniform reactor' coolant syste: cooldown, .this condition is ccn'servatively assured to be a degradation--in safety.
(
Corrective' Action A ; hough ~ 1t has been deter:ined that ~ the " wilt 2 reacter.ccolant pu=p motor             ~
mix with the lubricating oil for the reactor coclant pump motor bearings. Water. coring in contact with the bearings?cculd possibly cause thec _to seize. This -could reduce.the pu=ps' coastdown time during a reactor-trip, 'which could adve'rsely affect the safety of.~ the plant.; Continued' forced ' circulation of ' reactor coolant is required in the short ter after reactor trip.to remove the initial decay heat l ead. # Although all four reactor coolant pu=ps 'are not required for-uniform reactor' coolant syste: cooldown,.this condition is ccn'servatively assured to be a degradation--in safety.
Corrective' Action A ; hough ~ 1t has been deter:ined that ~ the " wilt 2 reacter.ccolant pu=p motor
~
heat exchangers have not leaked, TVA has' perferred an eddy current test en the tubing. A s=all number of tubes (apprcxina ely 3 out of 354 perL heat --
heat exchangers have not leaked, TVA has' perferred an eddy current test en the tubing. A s=all number of tubes (apprcxina ely 3 out of 354 perL heat --
exchanger) had indications .cf cracks extending 20 percent er greater through the wall thickness. In accordance with Westinghouse
exchanger) had indications.cf cracks extending 20 percent er greater through the wall thickness.
                                                                  ~
In accordance with Westinghouse
~
recc :endaticns, TVA 'has plugged these tubes..
recc :endaticns, TVA 'has plugged these tubes..
The co. ponent cooling system has been flushed and the a :cnia recoved.
The co. ponent cooling system has been flushed and the a :cnia recoved.
                , The hydrazine, .which apparently decomposed and produced the a==onia, was intended to be used only on an ' interim- basis and will not be reintroduced into the~syste=.         Therefo.e,; tubing =ade of.ad=irality brass will not. be susceptible to further stress corresf on cracking.
, The hydrazine,.which apparently decomposed and produced the a==onia, was intended to be used only on an ' interim-basis and will not be reintroduced into the~syste=.
                                                                                            ~
Therefo.e,; tubing =ade of.ad=irality brass will not. be susceptible to further stress corresf on cracking.
h._ _}}
~
h._
_}}

Latest revision as of 12:01, 24 December 2024

Part 21 Rept Re Stress Corrosion Cracking in Reactor Coolant Pump Motor Heat Exchanger Tubes,Initially Reported on 801202.Eddy Current Test Was Performed.Cracked Tubes Were Plugged
ML19343D215
Person / Time
Site: Sequoyah 
Issue date: 03/27/1981
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-81-395-000 10CFR-050.55E, 10CFR-50.55E, PT21-81-395, PT21-81-395-000, NUDOCS 8104100222
Download: ML19343D215 (3)


Text

,-

AlI A!)id Ib A r' PHI /1 P6'dNi rKU i ]t i AlL Ull1 - HUJ1 m t/W m

PE,T 21 IIBUIFICATIO$ NO. 9/

M'"#

C0'PANY tRE_

W A' DATE 0~ LETTtR.

3/77I/

ID2(ET NO.

f6 4 2 f

/

/

D - DISTRIBUTED ORIGINLL EPORTf SLP?LEnTARi DISTRIBUTION:

PEACTOR @

FLEL CYCLE &

SAFEGt1ARDS (S)

IE FILES

[ABIALS IE FILES EES O M IE FILES AD/SG AD/FFFSI AD/ROI PEGIO'E I,II,III,IV,V EGIONS I,II,III,IV,V EGIONS 1.,II,III.,IV,V VSO3R BR. R-IV

\\dOJR BR. R-IV VSOJR BR. PcIV LT3 / t'PA FIG 5715 I?SS/FD'S SS-595 pg/93L AE03 FIG 7502 LOEB/FPA l;iG 5715 g.33 / gg 33_ggi Cect;nnw m m 7zn N

A53D MG 7602 LO 3 / FP"^

FIG 5715 OtcolT;s mes 7zn NR?/DSI ASLBP E/d 450 AEOD FIG 7E02 tiDFDST Cifadtmw mnB'7zr SA3/SP t-iB-7210A ASLEP E/W 450 NRP/DJL 5

CEhTR L FILES 016 CEhTRAL FILES 016 ASL3'o E/d USD CSHRAL FILES ( GRD:0 CSURat FILES (CHRJ'O C5ii?A1. FILES 016 PDR CBERAL FILES SS-395 CSERAL FILES (GR0fD LPDR PDR gr,

~

PDR TERA '

e, LPDR a

9 O

L9R e

r TERA

~7 W

E,N A

ACTION:

+

PRELIMItMRY EVALUATION OF THE' ATTACHED REPORT ITOICATES LEAD R FOLL0hU? AS SFOWN BELOW:

IE NRR R.SS ]

cygg {

ES 81e41 o o ggg, ga, gK

o e

TENNESSEE VALLEY AUTHORITY

~

cH/ TTANOOOA. TENNESSEE 3 hot

[, g g 3 400 Chestnut Street Tower II l' arch 27, 1981 SQRD-50-328/81-11 N

Mr. JamesJ. O'Reilly, Director Office of Inspection and Enforcement U.S. NuclearMegulatory Comission Region II - Sdite 3100 101 Marietta St et Atlanta, Georgia 0303

Dear Mr. O'Reilly:

SEQUOYAH !!UCLEAR PUiNT UNIT 2 - STPISS CORROSION CRACKING IN TUBING ON THE PIAC"0B COOLANT PUMP OIL COOLERS - SQRD-50-326/81 FINAL P2 PORT The subject deficiency was initially reported to !!RC-0IE Inspector R. W. Wright on December 2, 1980, in accordance with 10 CFR 50.55(e) as NCR SQH NEB 8028. Interim nports were sub:r.itted on January 2 and

-February 3, 1981. Enclosed is our final report. We consider 10 CFR 21 applicable to this deficiency.

If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 857-2581.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure Mr.VictorStello,Jr., Director (Enclosure)i[

cc:

t Office of Inspection and Enforcement U.S. Nuclear Regulatory Co::: mission Washington, DC 20555 I

An Equct Or;:ortani*y Emdov v

h

.4

,I ENCLOSURE

^

SEQUOYAH NUCLEAR PLANT UNIT 2 STRESS CORROSION CRACKING IN T3ING ON THE REACTOR COOLANT. PUMP MOTC'R C:L CCOLERS -

SQED-501328/81-11 10 CFR 50.55(e)

' FINAL -REPORT Description o

_y The 'Sequoyah'unitI1 reactor coolant'pu=p motor. lubricating oil coolers developed excessive tube leakage during the hot functional test due to stress corrosion cracking (SCC) in the tube =aterial. Examination of the tube aterial removed from one such heat exchanger. revealed that the tubes were of admirality brass which has been found to be s.sceptible to stress corrosion cracking in this application. The cracking is due :to the presence of a==enia, which in conjunction with ~

residual and' operating stresses, causes the stress

  • corrosion cracking.

The a :enia present is apparently a product of the deco: position of -

hydrazine frot the co:ponent cooling syster water treatment.

I:plications to S'equoyah unit 2 were investigated, and it was determined that these heat exchanger tubes were also cade :f ad irality brass.

Safetv Inclications-Tube leakage'which could have resulted from SCC would al' low water to

(

mix with the lubricating oil for the reactor coclant pump motor bearings. Water. coring in contact with the bearings?cculd possibly cause thec _to seize. This -could reduce.the pu=ps' coastdown time during a reactor-trip, 'which could adve'rsely affect the safety of.~ the plant.; Continued' forced ' circulation of ' reactor coolant is required in the short ter after reactor trip.to remove the initial decay heat l ead. # Although all four reactor coolant pu=ps 'are not required for-uniform reactor' coolant syste: cooldown,.this condition is ccn'servatively assured to be a degradation--in safety.

Corrective' Action A ; hough ~ 1t has been deter:ined that ~ the " wilt 2 reacter.ccolant pu=p motor

~

heat exchangers have not leaked, TVA has' perferred an eddy current test en the tubing. A s=all number of tubes (apprcxina ely 3 out of 354 perL heat --

exchanger) had indications.cf cracks extending 20 percent er greater through the wall thickness.

In accordance with Westinghouse

~

recc :endaticns, TVA 'has plugged these tubes..

The co. ponent cooling system has been flushed and the a :cnia recoved.

, The hydrazine,.which apparently decomposed and produced the a==onia, was intended to be used only on an ' interim-basis and will not be reintroduced into the~syste=.

Therefo.e,; tubing =ade of.ad=irality brass will not. be susceptible to further stress corresf on cracking.

~

h._

_