ML19262C156

Responds to IE Bulletin 79-17,Revision 1, Pipe Cracks in Stagnant Borated Water Sys at PWR Plants. No Subsurface Cracking or Discontinuities Found in Accessible Welds in Stagnated,Borated,Oxygenated Lines.Supporting Data Encl

ML19262C156
Person / Time
Site:	Beaver Valley
Issue date:	01/03/1980
From:	Dunn C DUQUESNE LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-79-17, NUDOCS 8002070030
Download: ML19262C156 (10)

Text

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ave January 3, 1980 United States Nuclear Regulatory Commission Attention: Boyce H. Grier, Director Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 -

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 License No. DPR-56 Response to IE Bulletin 79-17 Revision 1

Dear Mr. Grier:

We have reviewed IE Bulletin 79-17 Revision 1, concerning systems or portions of safety related stainless steel piping systems which contain stagnated, oxygenated, borated water. As required by the Bulletin, we have previously transmitted to the Commission all of the responses required for Section 1 of the subject Bulletin, i.e., inservice and preservice inspection histories, chemistry control and data, past hydrostatic testing of stagnated lines and all system piping within our plant subjected to the stagnant, borated, oxygenated environment.

Furthermore, we identified all additional lines that were operated on a periodic basis, i.e., flushed once or twice a month.

This response and its attachments will address the results of the non-destructive evaluation (NDT) as required by Section 2(a) and 2(b) of the Bulletin. NDT evaluation involved visual inspection of all accessible welds, as well as liquid penetrant (PT) inspection and ultrasonic testing.(UT) of a 10%

sample of all accessible welds in stagnated, borated, oxygenated lines. Criteria for accessibility involved the weldments not being in containment or high radiation areas while PT and UT inspection accessibility was further restricted if weldments were insulated (lagged) or heat traced. Accessible lines that were insulated and/or heat traced were visually inspected by observing piping /

insulation surfaces for boric acid deposits. It should be noted that no boric acid deposits or other surface discontinuities (such as leakage) were observed either by visual or liquid penetrant inspection. The UT evaluation as performed by Westinghouse Personnel did not reveal any sub-surface cracking or discontinities in any of the weldments inspected.

Table I (attached) provides a summary of the inspection program according to line diameters greater than 2 1/2 inches and by system and piping wall thickness.

Also included in Table I are the number of welds per line, examinations performed, number of inaccess~1ble welds and reasons for inaccessibility. Several lines not originally reported have been added to Table I as a re-evaluation of the plant ECCS systems determined that these lines or portions of these lines fall within the scope of the Bulletin. These are not lines that are flushed on a periodic basis bet lines which do not exhibit continuous dynamic flow under normal operating conditions. Also, some lines have been deleted from the 1926 141 80o207o 050

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-56 Response to IE Bulletin 79-17, Revision 1 Page 2 original report, i.e., the Fuel Pool Cooling lines. Since the Fuel Pool Cooling system has never been placed in service and therefore never exposed to the borated, stagnant, oxygenated water, its lines were deleted from the inspection phase of this Bulletin. Table III (attached) provides a listing of all lines either added to or deleted from the original report. Since UT or PT was not required for lines less than 2 1/2 inches in diameter, only visual examination was performed on accessible welds. Table II (attached) provides a summary of this inspection.

Surface (PT) and ultrasonic examinations were performed on a representative sample of lines with piping diameters greater than 2 1/2 inches. The sample was to be at least 10% of the total number of accessible welds in each system with system weld populations segregated in accordance with specific piping wall thickness. However, for some groups of welds within a system, a 10% sample was not attainable due to inaccessibility of a majority of the welds. The Residual Heat Removal (RHR), Safety Injection System (SIS) and Quench Spray (QS) are three (3) systems where several of the particular wall thickness groups did not have 10% sample examinations because the lines were either located in containment, completely insulated or equipped with socket type Speedline welded fittings. This inability to perform a 10% sample affected eleven (11) groups of welds in the three (3) aformentioned systems. Even though several of the weld groups did not have a 10% sample NDT evaluation, the total number of welds that were ultrasonically and liquid penetrant inspected was in excess of 10% of the total number of accessible welds.

One (1) group of Quench Spray lines that was added to the original list was piping with a wall thickness of .120 inches. The welds although accessible were neither PT nor UT evaluated. Ultrasonics was not possible because the fittings were Speedline while penetrant testing was not performed as Revision 1 to the Bulletin eliminated the PT requirement.

Completion of the Ultrasonic Testing occurred on December 9,1979. Issuance of this response meets the thirty (30) day commitment for reporting the inspection.

results and any subsequent corrective action. Since no indications have been found, no corrective action has been initiated.

If you have any questions regarding this response, please contact my office.

Very truly yours, L

/t C. N. Dunn Vice President, Operations Attachments cc: United States Nuclear Regulatory Commission Director, Division of Operating Reactors Office of Inspection and Enforcement Washington, D. C. 20555 g}

TABI.E I INSPECTION RESULTS BORATED STACNANT 1.INES FOR PIPE DIAMETERS > 2 1/2 INCilES Wall No. No. No. No. Iligh No. No. In. llea t System Thick. l.ine No. Welds Visual P.T. U.T. Rad. Insul Cont. Trace S.I. .120 3"-SI- 35-152W-Q3 23 6 0 0 23 S.I. .134 6"-SI- 40-153W-Q2 59 59 9 9 6"-SI- 44-153W-Q2 65 65 9 9 e TOTAL. 147 124 18 18 S.I. .148 8"-SI- 2-153W-Q3 68 56 10 9 12 12 8"-SI- 2-153W-Q2 6 6 0 0 TOTAL. 74 56 10 9 12 12 S.I. .165 10"-SI- 16-153W-Q2 28 28 7 6 10"-SI- 17-153W-Q2 1 1 1 0 10"-SI- 26-153W-Q2 27 27 5 5 10"-SI- 27-153W-Q2 1 1 1 0 TOTAI. 57 57 14 11 S.I. .180 12"-SI- 1-153W-Q3 34 14 0 4 20 S.I. .216 3"-SI- 31-153W-Q3 3 3 0 0 3"-SI-145-153W-Q3 24 24 0 3 TOTAL 27 27 0 3 S.I. .280 6"-SI- 40-153A-Q2 13 13 1 1 6"-SI- 41-153A-Q2 8 8 2 2 6"-SI- 42-153A-Q2 5 5 1 1

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Wall No. No. No. No. liigh No. No. .n. Ileat System Thick. Line No. Welds Visual l' . T . U.T. Rad. Insul Cor . Trace R.S. .435 6"-PS- 29-153B-Q2 19 19 3 3 6"-RS- 30-1538-Q2 _ 18 18 3 1 TOTAL 37 37 6 4 Q.S. .120 4"-QS- 5-153B-Q3 5 5 0 0 4"-QS- 6-15311-Q3 7 7 0 0 4"-QS- 34-152 35 19 0 0 16 4"-QS- 35-152 6 6 0 0 TOTAL 53 37 0 0 16 Q.S. .165 10"-QS- 3-153B-Q3 53 53 9 7 10"-QS- 4-1538-Q3 42 42 5 4 TOTAL 95 95 14 11 Q.S. .180 12"-QS- 1- 15 311-Q 3 27 15 0 4 12 12"-QS- 2-153B-Q3 40 30 0 3 10 67 45 0 7 22 R . ll . R . .120 4"-Ril- 25-152 -Q2 25 25 R . ll . R . .134 6"-Ril- 14-15 2 -Q2 27 5 5 4 22 R ll.R. .365 10"- Ril- 4-602 -Q2 9 9 10"-Ril- 5-602 -Q2 10 5 10 l O"- Ril- 7-602 -Q2 8 8 8 10"-Ril- 8-602 -Q2 7 7 7 10"-Ril- 10-602 -Q2 8 8 8 4 10"-Ril- 17-602 -Q2 10 10 10 N 10"-Ril- 19-602 -Q2 _5 5 5 y _-_

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TABl.E I INSPECTION RESULTS BORATED STAGNAttr LINES FOR PIPE DIAMETERS > 2 1/2 INCllES (continued) ,

W.s i l No. No. No. No. liigli No. No. In. Ileat Sy s teni. Thick. Line No. Welds Visual P.T. U.T. Rad. Insul Cont. Trace R . II . R . .406 12"-Ril- 6-602 -Q2 5 5 12"-Ril- 9-602 -Q2 10 10 10 12"-Ril- 12-602 -Q2 29 29 29 TOTAL 44 39 44 R . ll . R . .438 14"-Ril- 2-602 -Q2 11 11 11 14"-Ril- 18-602 -Q2 15 15 TOTAL 26 11 26 R . ll . R . 1.125 10"-Ril- 23-1502-Q1 4 4 4 10"-Ril- 24-1502-Q1 8 8 8 TOTAL. 12 12 12 R . ll . R . 1.406 14 "-Ril- 1-1502-Q1 10 10 10 I

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No. No. liigli No. No. In.

System Line No. Welds Visual Rad. Insul. Cont.

R . II . 1 1/2"-Ril- 11-602 -Q2 4 4 2"- Ril- 3-602 -Q2 15 15 2"-Ril- 26-602 -Q3 6 6 TOTAL 25 25 Q.S. 1 1/2"-QS- 7-152 N/A ALL N

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TABLE III LISTING OF LINES ADDED TO OR DELETED FROM THE INSPECTION PROGRAM Lines Deleted Lines Added 2"-FC- 37-152 -Q3 3/4"-SI- 11-153W-Q2 6"-FC- 2-152 -Q3 3/4"-SI- 71-1503-Q2 6"-FC- 3-152 3/4"-SI-135-153W-Q2 6"-FC- 4-152 -Q3 3/4"-SI-137-153W-Q2 6"-FC- 5-152 -Q3 1"-SI- 61-1503-Q1 6"-FC- 8-152 -Q3 1"-SI- 61-1503-Q2 6"-FC- 9-152 -Q3 1"-SI-146-1503-Q2 6"-FC- 31-152 -Q3 3"-SI- 81-1503-Q2 10"-FC- 1-152 -Q3 3"-SI-130-1503-Q2 6"-SI- 40-153A-Q2 6"-SI- 41-153A-Q2 6"-SI- 42-153A-Q2 8"-SI- 2-153W-Q2 2"-CH- 82-1503-Q2 2"-CH-124-1503-Q2 3"-CH- 73-1503-Q2 3"-CH- 74-1503-Q2 3"-CH- 75-1503-Q2 4"-CH- 76-1503-Q2 6"-RH- 20-602 -Q2 4"-QS- 5-1533-Q3 1926 150