05000324/LER-1983-097, Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking

Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking

ML20080A194
Person / Time
Site:	Brunswick
Issue date:	01/24/1984
From:	Dietz C, Pastva M, Postva M CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP-84-0057, BSEP-84-57, IEB-83-02, IEB-83-2, LER-83-097-01T, LER-83-97-1T, NUDOCS 8402030407
Download: ML20080A194 (4)

LER-2083-097, Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking

Event date:
Report date:
3242083097R00 - NRC Website

text

NRC FORM 366 U.S. NUCLEAR REIULATO'.Y COMMISSION Update Report:

. LICENSEE EVENT REPORT

,g Previous Report Date 12-22-83

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8 60 68 69 EVENT DATE 74 75 REPORT DATE 80 -

i 61 DOCAET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 lDuring the performance of testinn required by IE Bulletin 83-02, it was determined thatl

. -j ITT31 l crack indications existed in 19 of 131 welds examined on the Reactor Recirculation Sys-l ITTTl item and Reactor water Cleanup and Residual neat Removal system. Data evaluation has l ITTTI i determined these indications range from 5 to 22.0 percent of pipe wall thichness with l s

o e l iengths that range from .5" to 11.0". This event did not a f fec t the health and safety l j

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C. 0l Ol Aj d h (,y,,jh Wh lAl !1 lnlh 33 34 35 36 3 40 41 42 43 44 47 CAUSi DESC'RIPTION AND CORRECTIVE ACTIONS h l i l o l lThe indications are attribut ed to IGSCC. Eight welds with these indications were re- l gp aired using acceptable weld overlay techniques. The remaining wid indications were l y

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LER ATTACHMENT - RO #2-83-97 Facility: BSEP Unit No. 2 Event Date: November 27, 1983 During a unit maintenance outage, performance of testing required by IE Bulletin 83-02' revealed that crack indications existed in 7 of 33 piping welds initially selected for testing in accordance with the sampling provision of the IE bulletin. The weld crack indications found during this initial testing are shown in Table 1.

TABLE 1 Thru Weld Configuration Orientation Length Wall % Location

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G31-6"-10 1.25" Elbow side Pipe to elbow Circumferential 13.0%

B32-12"-BR-G4 Pipe to safe end Circumferential 2.0" 14.0% Pipe side B32-12"-BR-G4 Pipe to safe end Circumferential 1.25" 7.0% Pipe side B32-12"-BR-K3 Elbow to pipe Circumferential 1.25" 5.0% Pipe side elbow E11-20"-A2 Pipe to valve Transverse 0.95" 16.0% Pipe side B32-22"-BM-1 Manifold to cap Circumferential 1.2" 16.0% Cap side B32-28"-A8 Elbow - Valve / 45' Skewed 1.0" 17.0% Elbow side suction side B32-28"-A14 Valve - Elbow / Circumferential 0.5" 20.0% Elbow side discharge side Based on the initial weld testing. an additional 26 welds were tested in accordance with the sample expansion provision IEB 83-02 and IWB 2430 of ASME Section XI. Crack indications at four additional welds were found during this phase of testing which are shown in Table 2.

TABLE 2 Thru Weld Configuration Orientation Length Wall % Location B32-12"-BR-J3 Elbow to pipe Circumferential 1.75" 11.0% Elbow side B32-28"-A4 Elbow to pipe Circumferential 1.0" 9.0% Pipe side B32-28"-A4 Elbow to pipe Circumferantial 1.5" 19.0% Elbow side B32-28"-B3 Pipe to elbow Circumferential 0.7" 16.0% Elbow side B32-28"-B3 Pipe to' elbow Circumferantial 0.8" 12.0% Elbow side

& Transverse B32-28"-B4 Elbow to pipe Circumferential 1.0" 11.0% Elbow side Based on the results of the second phase of weld testing, an additional 46 welds were inspected in accordance with the sampling provision of IEB 83-02 and IWB 2430 of ASME Section XI. This phase of testing revealed five additional welds with crack indications which are shown in Table 3.

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TABLE 3 Thru LWeld Configuration ~ Orientation- Length Wall % Location B32-12"-BR-J2 Pipe to elbow Circumferential 2.25" 12.0% Elbow side

.B32-12"-BR-K2 Pipe to elbow Circumferential 1.25" 11.0% Elbow side

~B32-28"-A13 Pipe to valve' Circumferential 0.5" 19.0% Pipe side B32-28"-B9 Valve to pipe- Skewed 1.0" 17.6% Pipe side B32-28"-B5 Pipe to pipe Circumferential 2.375" 22.0% PJpe (upstream).

B32-28"-B5- Pipe to pipe Circumferential 3.0" 15.0% Pipe (upstream)

B32-28"-B5 Pipe to pipe Circumferential 1.5" 19.0% Pipe (upstream) c Considering the results of-the third phase of weld testing, the remaining 26 welds were voluntarily tested for 100% compliance with IEB 83-02 and IGSCC

. Inspection Order Confirming Shutdown, dated August 26, 1983. During this

phase of weld testing, three additional welds with crack indications were revealed and are shown in Table 4.

TABLE 4 Thru

. Weld Configuration Orientation Length Wall % Location

-G31-6"-15 Elbow to pipe Circumferential 1.25" 16.0% Elbow side G31-6"-16 Pipe to pipe Circumferential 0.75" 8.0% Pipe (downstream)

B32-22"-AM-5 Pipe - Cross / Circumferential 11.5" 20.0% Pipe side discharge and Skewed Inter-mittent The 19, crack-indications discovered during testing are attributed to IGSCC.

Eight of these indications, shown in Table 5, were repaired using acceptable weld overlay techniques. During the repair of welds B32-12"-ER-K2, B32-12"-BR-K3, and G31-6"-15, indications were detected that are believed to have resulted from through-wall defects. Details concerning the discovery and repair of these defects are ccutained in the submittal of Serial No.

LAP-a3-549. The remaining 11 crack indications were evaluated by NUTECH and determined acceptable for deferring their weld overlay repair until a s scheduled Spring 1984 Unit No. 2 outage.

T/.BLE 5 Welds Repaired Using Overlay Technique.

'G31-6"-15 B32-12"-BR-J3 G31-6"-16 B32-12"-BR-K2 G31-6"-10 B32-12"-BR-K3 B32-12"-BR-J2 B32-12"-BR-G4 LAdditional information concerning this event is provided in Carolina Power &

-Light Company's response to IE Bulletin 83-02, Serial No. BSEP/83-3748.

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Carolina Pcwer & Light Company

') .3 Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 January 24, 1984 FILE: B09-13510C SERIAL: BSEP/84-0057 Mr. James P. O'Reilly, Administrator

- U. S. Nuclear Regulatory Commission

~ Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324 LICENSE NO. DPR 62 SUPPLEMENT TO LICENSEE EVENT REPORT 2-83-97

Dear Mr. O'Reilly:

In accordance with Sec. tion 6.9.1.8c of the Technical Specifications for Brunswick Steam Electric Plant, Unit No. 2, the enclosed supplemental Licensee Event Report is submitted. It has been identified that one of the report attachment sheets was inadvertently omitted from the original submittal of the report made on December 22, 1983, Serial No. BSEP/83-3942. In addition, a clarification of weld numbers reflected in the report attachment sheets has been made. The revised report which is in accordance with the format set forth in NUREG-0161, July 1977, is being redistributed in its entirety.

Very truly ycurs, di# 4 C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/mcg/LETPS1 Enclosure

'cc: Mr. R. C. DeYoung NRC Document Control Desk OFFICINL COPY 12 2'1 1

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