1CAN038705, Forwards Rept of Results of once-through Steam Generator Tubing Insps Conducted During Sixth Refueling Outage,Per Tech Spec 4.18.6.Delay in Submittal of Rept Isolated Occurrence & Not Indicative of Procedural Problems

Forwards Rept of Results of once-through Steam Generator Tubing Insps Conducted During Sixth Refueling Outage,Per Tech Spec 4.18.6.Delay in Submittal of Rept Isolated Occurrence & Not Indicative of Procedural Problems

ML20206Q799
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/31/1987
From:	Enos J ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN038705, 1CAN38705, NUDOCS 8704220038
Download: ML20206Q799 (11)

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, Liccnsing R:quir:ments ANO-1 T.S. 4.18.6 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 March 31, 1987 1CAN038705 U.S. Nuclear Regulatory Commission (NRC)

Document Control Desk Washington, D. C. 20555

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Inservice Inspection of Steam Generator Tubes 1R6 Gentlemen:

In accordance with Arkansas Nuclear One-Unit 1 (ANO-1) Technical Specification 4.18.6, attached is a report of the results of the once-through steam generator (OTSG) tubing inspections conducted during the sixth refueling outage (1R6).

A review of our transmittal records does not show that the subject report was submitted to the NRC as required by Technical Specification 4.18.6. Our investigation shows this was an isolated instance where the report was prepared but actual transmittal was not effected, and does not indicate programmatic procedural problems. The significance of the data was minimal because the first sample inspection showed results in the highest category, C-1, for both steam generators.

8704220038 870331 PDR ADOCK 05000313 O PDR 15 MEveEA MiDOLE SOUTH UTILITIES BYSTEM

-NRC M:rch 31, 1987 This discrepancy was identified in the course of preparing the Report of the Inservice Inspection of Steam Generator Tubes for the seventh refueling outage, which was submitted by our letter of February 4,1987 (ICAN028703).

Very truly yours, N

. Ted Enos, Manager Nuclear Engineering Licensing JTE:MGB:1w Attachment cc: Mr. Robert D. Martin Regional Administrator Region IV, U.S. NRC 611 Ryan Plaza Dr., Suite 1000 Arlington, TX 76011 Mr. Robert John:on Resident Inspector Arkansas Nuclear One Russellville, AR 72801

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ARKANSAS NUCLEAR ONE-UNIT ONE STEAM GENERATOR TUBING INSERVICE INSPECTION REPORT FOR THE SIXTH REFUELING OUTAGE INSPECTION

SUMMARY

An inservice eddy current inspection was performed on tubes in the Arkansas Nuclear One Unit 1 (ANO-1) Once Through Steam Generators (OTSGs) "A" and "B" during October 1984 and completed on October 28, 1984. The previous inservice inspection, conducted from December 10, 1982 through February 25, 1983, resulted in a twenty-four (24) month inspection interval (per ANO-1 Technical Specification 4.18.4.a).

The inspection was conducted in accordance with Technical Specification 4.18.3 and Technical Specification 4.18.2. The sample included a 3% random sample from the steam generators with exceptions as provided in Technical Spectfication 4.18.3.a.

In the "A" 0TSG, 766 tubes were inspected full length. In addition, 4,629 non plugged tubes in the wedge region (described in Technical Specification Figure 14.18.1 and Technical Specification 14.18.3.a.3(3)) were inspected from the 15th tube support plate up. (Some tubes in this region were examined below the 15th tube support plate as well, as part of the first sample inspection).

In the "B" OTSG, 766 tubes were inspected full length. In addition, 4,659 non plugged tubes in the wedge region (described by Technical Specification 14.18.3.a.3(3) and Technical Specification 14.18.1) were inspected from the 15th tube support plate up. (Some tubes in this region were examined below the 15th tube support plate as well, as part of the first sample inspection).

The multi-frequency method of eddy current testing was utilized during the inspection to determine tube wall degradatim.

INSPECTION RESULTS Tube wall degradation was observed in both the "A" and "B" OTSGs. In the "A" OTSG eighteen defective (i.e., ~>40% through wall imperfections per Technical Specification 4.18.5.a.5) imperfections were identified. Twelve defective tubes were plugged and six were sleeved. A total of ten tubes, including four degraded tubes in the "A" OTSG were part of the ANO-1 demonstration sleeving program. In the "B" 0TSG five defective (i.e., ,)40%

through wall imperfections per Technical Specification 4.18.5.a.5) imperfections were identified. All five tubes were plugged. Both sample inspections for the "A" OTSG and the "B" 0TSG had Category C-1 results.

Under the current Technical Specifications the next inservice inspection should be performed at a 10 to 24 month inspection interval in accordance with ANO-1 Technical Specification 4.18.4.a.

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Tables 1 and 2, attached, list the defective tubes for the "A" and "B" OTSGs, respectively. Defect location, size (% through-wall) and disposition are also listed. Tables 3 and 4 list the remaining reportable indications

(>20 but <40% through-wall imperfections per Technical Specification 4718.5.a.1) in the "A" and "B" OTSGs. Defect location, size and disposition, if any, are also provided.

These lists complete the reporting requirements of Technical Specification 4.18.6.

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TABLE 1 "A" 0TSG TUBE DEFECTS

(>40% Throughwall Indications)

R0W-TUBE LOCATION  % THROUGHWALL DISPOSITION 39-16 UTSM (1) 47 Sleeved 39-18 UTSM 42 Sleeved 40-14 UTSM 70 Plugged 59-13 UTSH 43 Sleeved 65-19 UTSH 50 Plugged i 68-30 UTSM 68 Sleeved i

70-27 UTSH 43 Sleeved

'f 70-29 UTSM 42 Sleeved

< 71-55 UTSF (2) 63 Plugged 72-1 UTSH 46 Plugged 77-1 15 (3) >40 Plugged 77-14 UTSF 68 Plugged 1

77-62 UTSF 60 Plugged 78-61 UTSF-ID (4) 60 Plugged 81-5 UTSM 42 Plugged

, 83-11 UTSM 42 Plugged 96-1 UTSM 62 Plugged 99-11 UTSM 40 Plugged (1) UTSH = Upper Tubesheet Midspan (2) UTSF = Upper Tubesheet face (3) Designation for defect at a tube support plate, in this case the 15th tube support plate.

(4) 10 = Inside Diameter 3

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TABLE 2 "B" 0TSG TUBE DEFECTS

(>40% Throughwall Indications)

R0W-TUBE LOCATION  % THROUGHWALL DISPOSITION 67-1 UTSM (1) 45 Plugged 70-23 UTSM 55 Plugged 75-8 15 (2) - ID (3) 57 Plugged 87-3 UTSM 63 Plugged 96-6 UTSM 50 Plugged (1) UTSM = Upper Tubesheet Midspan (2) Designation for defect at a tube support plate, in this case the 15th tube support plate.

(3) ID = Inside Diameter 4

~. __ . _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ - - - - _ _ - - _ - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ - - - _ - _ _ _ _ _ _ - _ - _ _

TABLE 3 "A" 0TSG DEGRADED TUBES

(>20% Throughwall But <40% Throughwall Indications)

R0W TUBE LOCATION  % THROUGHWALL DISPOSITION (if any) 10-31 UTSM (1) 25 12-46 UTSM 36 Plugged 13-5 5-6 (2) 34 Plugged 21-55 UTSM 29 31-13 UTSM 32 31-55 LTS-1 (3) 27 Plugged LTS-1 20 35-14 UTSH 23 37-12 UTSM 27 38-13 UTSM 30 39-13 UTSM 36 46-4 UTSM 26 51-20 UTSM 27 56-2 UTSM 23 59-24 UTSH 37 Sleeved, 61-17 UTSM 31 64-7 UTSM 26 64-11 UTSM 35 65-11 UTSM 30 66-24 UTSM 35 5

TABLE 3 (continued)

"A" 0TSG DEGRADED TUBES

(>20% Throughwall But <40% Throughwall Indications) 67-34 UTSM 34 Plugged 67-56 UTSM 38 Plugged 67-58 UTSM 24 68-2 UTSM 36 Plugged 69-8 UTSM 26 69-9 UTSM 32 69-10 UTSM 24 69-13 UTSM 20 70-13 UTSM 20 70-42 UTSH 22 70-58 UTSM 34 71-23 UTSM 35 Sleeved UTSM 21 71-25 UTSM 31 Sleeved UTSM 36 71-61 UTSM 25 72-5 UTSM 30 Plugged UTSM 38 72-6 UTSM 36 72-7 UTSM 29 UTSM 22 72-16 UTSM 25 72-22 UTSM 20 72-34 UTSM 22 75-14 UTSM 28 6

o______ _ _ _ _ - - _ - - - - - _ - - . - - _ _ - - _ - - - _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ - - - _ - - - - - - _ - - - - _ - . - _ - - - _ _ - - _ _ _ - . _ _ _ - - - - - - - - - - - _ _ _ _ _ - _ _ _ - - _ _ _

ty . 77.. .

j. 'y. 44;.9- ,3 . ,

kY %y' TABLE 3 (continued).

N9 ef e- "A" OTSG DEGRADED TUBES p.gx 4

(>20% Throughwall But <40% Throughwall Indications)

N ,,

.s - 79-3 UTSM s 27 80-15 UTSM 27 UTSM /25 81-8 UTSM ,' 20 D{ .

• n- .

81-52 UTSk 27 , ,

rh 81-54 UTSM 31

+ UTSM 27 y ,

A 81-65 UTSM 33 82-7 UTSM 26

• UTSM .

• 25

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i3 s N '82-151 UTSM 20 Sleeved 29 i.Q UTSM ..

82-19 UTSM 24

ty ~

'/ " 82-27 UTSM 21 82 UTSM 28 h 3 82 UTSM 32 83-5 UTSM 30 j 83-24 UTSM '37 Plugged:

3 8N13 UTSM 26

~ V 89-4 UTSM 29 s

s ' #"' <

97-4 UTSM 24 ,[

k- 'l 102-4 UTSM 23 , t

..y 3 102-116 7-8 22 ..i a N '\ ;1 1

); 3 104-2 UTSM 27 '

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TABLE 3 (continued)

"A" 0TSG DEGRADED TUBES

' (>20% .Throughwall But <40% Throughwall Indications) 104-15 UTSM 22 UTSM 28

- 107-13 UTSM 34 117-100 UTSM 30 Plugged 119-92 UTSM 37 Plugged 126-97 UTSM. 34 Plugged Tube'63-9 was also plugged for preventive reasons.

(1) UTSM = Upper Tubesheet Midspan (2) Designation for defect at or between tube support plates, in this case between the fifth and sixth support plate.

(3) LTS-1 = between the lower tubesheet and the first support plate.

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TABLE 4' "B" 0TSG DEGRADED' TUBES

(>20% Throughwall But <40% Throughwall Indications)

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R0W TUBE. LOCATION  % THROUGHWALL DISPOSITION

-(if any) 1 40-73 12-13(1) -ID (2) 38 . Plugged 69 UTSM (3) 20 69-10 UTSM 32 72-20 UTSM 23 74-8 UTSM 20 t 75-10 14 24 Plugged 15 27~

3 UTSM 25 79-21 UTSM 32

+

79-26 UTSM 22 83-3 UTSM 33 83-15 UTSM 30 UTSM 25 h

83-26 UTSH 22 I

85-23 UTSM 26 85-24 UTSM 20 t-86-2 UTSM 30 87-24 UTSM 24 94-2 UTSM 28 123-56 11-12. 23 129-7 UTSM 22 (1) Designation for defect at or between tube support plates, in this case p between the twelfth and thirteenth tube support plates.

, (2) ID = Inside Diameter (3) UTSM = Upper Tubesheet Midspan

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_ . . - . . . . _ - . _ . = . _ . , . _ _ - . _ , . . . . _ _ . _ _ - - - _ , _ . _ _ , - _ - _ _ _ . . _ _ _ _ . _ - - _ . . _ , - _ . . . . _ , _ _ .