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| issue date = 05/09/1990
| issue date = 05/09/1990
| title = Forwards Thimble Tube Eddy Current Insp Rept Re NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors. Insp Conducted at End of Cycle Xi.One Thimble Required to Be Isolated Until Wear Rate Determined
| title = Forwards Thimble Tube Eddy Current Insp Rept Re NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors. Insp Conducted at End of Cycle Xi.One Thimble Required to Be Isolated Until Wear Rate Determined
| author name = HARRIS K N
| author name = Harris K
| author affiliation = FLORIDA POWER & LIGHT CO.
| author affiliation = FLORIDA POWER & LIGHT CO.
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ACCELERATED DI'STRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RI DS)ACCESSION NBR: 9005160081 DOC.DATE: 90/05/09 NOTARIZED:
{{#Wiki_filter:ACCELERATED DI'STRIBUTION DEMONS                                   TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM ( RI DS )
NO FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C AUTH.NAME AUTHOR AFFILIATION HARRIS,K.N.
ACCESSION NBR: 9005160081             DOC. DATE: 90/05/09   NOTARIZED: NO           DOCKET g FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light                 C 05000250 AUTH. NAME           AUTHOR AFFILIATION HARRIS,K.N.         Florida     Power 6 Light Co.
Florida Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET g 05000250
RECIP.NAME           RECIPIENT AFFILIATION Document Control Branch (Document           Control Desk)


==SUBJECT:==
==SUBJECT:==
Forwards thimble tube eddy current insp rept re NRC Bulletin 88-009.DISTRIBUTION CODE: IE18D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Bulletin 88-09-Thimble Tube Thinning xn Westinghouse Reac ors NOTES: RECIPIENT ID CODE/NAME PD2-2 LA EDISON,G COPIES LTTR ENCL 1 0 1 1 RECIPIENT I D CODE/NAME PD2-2 PD COPIES LTTR ENCL 1 1 INTERNAL: AEOD/DOA NRR BUCKLEY,B NRR RAMSEY,J RGN2 FILE 01 EXTERNAL: LPDR NSIC 1 1 1 1 1 1 1 1 1 1 1 1 AEOD/DSP NR O.~ThE NRC PDR 02 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
Forwards thimble tube eddy current insp rept re NRC Bulletin 88-009.
PLEASE HELP US TO REDUCE WAS''CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12 I
DISTRIBUTION CODE: IE18D           COPIES RECEIVED:LTR         ENCL     SIZE:
P.O.Box 14000, Juno Beach, FL 33408.0420 FPL NAY 09$990 L-90-163 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
TITLE: Bulletin   88-09   Thimble     Tube Thinning xn Westinghouse     Reac ors NOTES:
RECIPIENT                COPIES            RECIPIENT         COPIES ID CODE/NAME PD2-2 LA LTTR ENCL       ID CODE/NAME PD2-2 LTTR ENCL 1     0            PD              1    1 EDISON,G                    1      1 INTERNAL: AEOD/DOA                     1      1    AEOD/DSP              1    1 NRR BUCKLEY,B               1      1    NR    O.              1    1 NRR RAMSEY,J                 1      1        ~ThE        02      1    1 RGN2     FILE 01            1      1 EXTERNAL: LPDR                         1     1     NRC PDR               1     1 NSIC                        1     1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WAS'' CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR               13   ENCL   12
 
I P.O. Box 14000, Juno Beach, FL 33408.0420 FPL NAY     09   $ 990 L-90-163 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:


==Subject:==
==Subject:==
Turkey Point Unit 3 Docket No.50-250 IE Bulletin 88-09 Thimble Tube Thinnin in Westin house Reactors Provided as an attachment is the Thimble Tube Eddy Current Inspection Report for Turkey Point Unit 3.Should there be any questions, please contact me.Very truly yours,+il/K.N.>arris Vice President Turkey Point Plant Nuclear KNH/WFK/gp Attachment cc: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9005)600@1 900%0,-PE<P gDOCK 0 t DC an FPL Group company TURKEY POINT UNIT 3 END OF CYCLE XI FLUX MAP THIMBLE TUBE EDDY CURRENT TEST REPORT FOR NRC BULLETIN 88-09 4 QLM COON OtQf/sprit 2J, f HO t L t 1 tN Introduction An eddy current examination (ECT)of the Turkey Point Unit 3 flux map thimble tubes was performed during the Cycle XI to Cycle XII refueling outage.The examination was performed by the Florida Power and Light (FPL)Materials, Codes, and Inspections group using standard eddy current techniques.
Turkey Point Unit 3 Docket No. 50-250 IE Bulletin 88-09 Thimble Tube Thinnin in Westin house Reactors Provided       as an attachment is the Thimble Tube               Eddy       Current Inspection Report for Turkey Point Unit 3.
Two of the fifty installed thimble tubes could not be inspected due to blockage.Of the remaining forty eight, none of the thimbles had wear in excess of the 60%wall loss which would indicate a loss of structural integ rity.Acce tance Criteria Westinghouse was commissioned to perform a Turkey Point specific analysis for the maximum allowable wall loss that could be sustained, and still maintain the pressure boundary integrity.
Should there be any questions, please contact me.
The Westinghouse analysis determined that up to a 60%wall loss over a 0.75 inch length could be sustained and still maintain the thimble tube integrity.
Very truly       yours,
Performance Forty eight (48)of the fifty (50)tubes were cleaned and flushed by Westinghouse prior to the eddy current examination.
    +il/
The remaining two thimble tubes, in core locations E-11 and D-12, are blocked.E11 is blocked by a fixed incore detector from a demonstration project and D12 by a cut-off moveable incore detector.Removal of these devices at this time was not possible because of ALARA concerns.The examination probe was inserted and withdrawn manually, with data being recorded during the withdrawal phase.The entire length of each thimble tube was examined.Results The ECT data was analyzed by the FPL Materials, Codes, and Inspections group to determine the percent wall loss and wear scar length for each thimble tube.The results from the data analysis identified the thimble tube locations with 10%or greater wall loss.A total of 13 thimble tubes showed a wall loss greater than 10%.Attachment 1 summarizes the results of the inspection.
K. N. arris Vice President Turkey Point Plant Nuclear KNH/WFK/gp Attachment cc:   Stewart D. Ebneter, Regional Administrator, Region II,                     USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9005)600@1     900%0,-
All of the 48 thimble tubes inspected met the acceptance criteria.A~nal sls The ECT results were reviewed by Nuclear Engineering to determine if there were any operability concerns.The evaluation by Nuclear Engineering recommended the closing of isolation valves on the two thimbles not inspected.
PE<P   gDOCK 0 t DC an FPL Group company
Also thimble N5, which indicated a wall loss of 48%, was recommended to have its isolation valve closed until further measurements can be taken to determine its wear rates.0 GLM CORK 5559K P4Aptll 19, 5990 50: 59 PM k Page 1 Conclusion The ECT inspection of forty-eight out of fifty flux map thimble tubes indicated that one thimble needed to be isolated until a wear rate'could be determined.
 
The two thimble locations not inspected shall also be isolated until they can be properly evaluated or replaced.Ins ectionPro ram The upper limit of the acceptance criteria for thimble tube wall loss has been established at 60 8 wall loss for scars less than 0.75 inches long over 60'f the tube circumference by the Westinghouse analysis.The establishment of a specific inspection frequency based on the current inspection results would be predicted on an assumed wear rate.To measure the thimble tube wear rate, the results of this initial inspection will be considered as baseline data, and another thimble tube inspection will be performed during the next refueling outage.After the measured wear rate has been determined, a specific inspection frequency will be established based on the worst wear locations and the measured wear rate.AGLM CONN CNSX E44prM W 1%0 10:f 0 Nl Page 2 REACTOR FUEL LOCATION TURKEY POINT PLANT UNIT NO.3 CYCLE NO.XI TO CYCLE XII ECT RESULTS OF FLUX MAP THIMBLE TUBE INSPECTlON FOR THIMBLE WITH WEAR>10%15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 25%.10.4 48%5.0 N 29%4.I 31%4.5 23'%3 12%8.8 13%1.8'8%4.2 28%2.5 29'%.2 D 19'%.7 X a thimble obstructed
TURKEY POINT UNIT 3 END OF CYCLE XI FLUX MAP THIMBLETUBE EDDY CURRENT TEST REPORT FOR NRC BULLETIN88-09 4 QLM COON OtQf /sprit 2J, f HO t L t 1 tN
'testedlocatlonwitha measurable wall loss s 10%15%3.3 25%'8.4 LEGEND Percent Wall loss B Scar Length in Inches A}}
 
Introduction An eddy current examination (ECT) of the Turkey Point Unit 3 flux map thimble tubes was performed during the Cycle XI to Cycle XII refueling outage. The examination was performed by the Florida Power and Light (FPL)
Materials, Codes, and Inspections group using standard eddy current techniques. Two of the fifty installed thimble tubes could not be inspected due to blockage. Of the remaining forty eight, none of the thimbles had wear in excess of the 60% wall loss which would indicate a loss of structural integ rity.
Acce tance Criteria Westinghouse was commissioned to perform a Turkey Point specific analysis for the maximum allowable wall loss that could be sustained, and still maintain the pressure boundary integrity. The Westinghouse analysis determined that up to a 60% wall loss over a 0.75 inch length could be sustained and still maintain the thimble tube integrity.
Performance Forty eight (48) of the fifty (50) tubes were cleaned and flushed by Westinghouse prior to the eddy current examination. The remaining two thimble tubes, in core locations E-11 and D-12, are blocked. E11 is blocked by a fixed incore detector from a demonstration project and D12 by a cut-off moveable incore detector. Removal of these devices at this time was not possible because of ALARA concerns. The examination probe was inserted and withdrawn manually, with data being recorded during the withdrawal phase. The entire length of each thimble tube was examined.
Results The ECT data was analyzed by the FPL Materials, Codes, and Inspections group to determine the percent wall loss and wear scar length for each thimble tube.
The results from the data analysis identified the thimble tube locations with 10% or greater wall loss. A total of 13 thimble tubes showed a wall loss greater than 10%. Attachment 1 summarizes the results of the inspection. All of the 48 thimble tubes inspected met the acceptance criteria.
A~nal sls The ECT results were reviewed by Nuclear Engineering to determine if there were any operability concerns.               The evaluation by Nuclear Engineering recommended the closing of isolation valves on the two thimbles not inspected. Also thimble N5, which indicated a wall loss of 48%, was recommended to have its isolation valve closed until further measurements can be taken to determine its wear rates.
k 0 GLM CORK 5559K P4Aptll 19, 5990 50: 59 PM                               Page 1
 
Conclusion The ECT inspection of forty-eight out of fiftyflux map thimble tubes indicated that one thimble needed to be isolated until a wear rate'could be determined.
The two thimble locations not inspected shall also be isolated until they can be properly evaluated or replaced.
Ins ectionPro           ram The upper limit of the acceptance criteria for thimble tube wall loss has been established at 60 8 wall loss for scars less than 0.75 inches long over 60'f the tube circumference by the Westinghouse analysis. The establishment of a specific inspection frequency based on the current inspection results would be predicted on an assumed wear rate. To measure the thimble tube wear rate, the results of this initial inspection will be considered as baseline data, and another thimble tube inspection will be performed during the next refueling outage. After the measured wear rate has been determined, a specific inspection frequency will be established based on the worst wear locations and the measured wear rate.
AGLMCONN CNSX E44prM W 1%0 10:f 0 Nl                                     Page 2
 
REACTOR FUEL LOCATION TURKEY POINT PLANT UNIT NO. 3 CYCLE NO. XI TO CYCLE XII ECT RESULTS OF FLUX MAP THIMBLETUBE INSPECTlON FOR THIMBLEWITH WEAR     >10%
15         14         13     12     11     10       9         8     7   6       5   4   3         2         1 25%.                 48%
10.4                 5.0 N
29%
4.I 31%           23'%3 4.5 12%
1.8'8%
8.8 13%                                             28%
4.2     2.5 29'%.2 D
19'%.7 15%                      25%
3.3                    '8.4                LEGEND                        B X a thimble obstructed
'   testedlocatlonwitha                                                                       Percent Wall loss measurable wall loss s 10%
Scar Length in Inches A}}

Latest revision as of 22:54, 3 February 2020

Forwards Thimble Tube Eddy Current Insp Rept Re NRC Bulletin 88-009, Thimble Tube Thinning in Westinghouse Reactors. Insp Conducted at End of Cycle Xi.One Thimble Required to Be Isolated Until Wear Rate Determined
ML17348A240
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 05/09/1990
From: Harris K
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-009, IEB-88-9, L-90-163, NUDOCS 9005160081
Download: ML17348A240 (7)
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Text

ACCELERATED DI'STRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM ( RI DS )

ACCESSION NBR: 9005160081 DOC. DATE: 90/05/09 NOTARIZED: NO DOCKET g FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 AUTH. NAME AUTHOR AFFILIATION HARRIS,K.N. Florida Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards thimble tube eddy current insp rept re NRC Bulletin 88-009.

DISTRIBUTION CODE: IE18D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Bulletin 88-09 Thimble Tube Thinning xn Westinghouse Reac ors NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME PD2-2 LA LTTR ENCL ID CODE/NAME PD2-2 LTTR ENCL 1 0 PD 1 1 EDISON,G 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP 1 1 NRR BUCKLEY,B 1 1 NR O. 1 1 NRR RAMSEY,J 1 1 ~ThE 02 1 1 RGN2 FILE 01 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

I P.O. Box 14000, Juno Beach, FL 33408.0420 FPL NAY 09 $ 990 L-90-163 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Subject:

Turkey Point Unit 3 Docket No. 50-250 IE Bulletin 88-09 Thimble Tube Thinnin in Westin house Reactors Provided as an attachment is the Thimble Tube Eddy Current Inspection Report for Turkey Point Unit 3.

Should there be any questions, please contact me.

Very truly yours,

+il/

K. N. arris Vice President Turkey Point Plant Nuclear KNH/WFK/gp Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 9005)600@1 900%0,-

PE

10% 15 14 13 12 11 10 9 8 7 6 5 4 3 2 1 25%. 48% 10.4 5.0 N 29% 4.I 31% 23'%3 4.5 12% 1.8'8% 8.8 13% 28% 4.2 2.5 29'%.2 D 19'%.7 15% 25% 3.3 '8.4 LEGEND B X a thimble obstructed ' testedlocatlonwitha Percent Wall loss measurable wall loss s 10% Scar Length in Inches A

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