ML20213C929

Advises of Plans to Perform Reinsp for IGSCC Piping During Reload 5 Outage Scheduled to Begin on 870131,per Generic Ltr 84-11.Rev 0 to XCP-40-101, Technical Justification for Continued Operation of Brunswick Unit 1 W/..., Encl

ML20213C929
Person / Time
Site:	Brunswick
Issue date:	10/31/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Muller D Office of Nuclear Reactor Regulation
Shared Package
ML20213C932	List: ML20213C929 ML20213C976
References
GL-84-11, IEIN-84-41, NLS-86-401, NUDOCS 8611100359
Download: ML20213C929 (5)

Text

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CD&L Carolina Power & Light Company - . SERIAL: NLS-86-401 OCT 31 126 Director of Nuclear Reactor Regulation Attention: Mr. Dan Muller BWR Project Directorate #2 Division of BWR Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NO. 50-325/ LICENSE NO. DPR-71 l IGSCC INSPECTIONS PLANS  !

SUMMARY

Generic Letter intergranular 84-11 stress initiated corrosion a reinspection cracking (IGSCC .p)rogram for piping In accordance susceptible with this to requirement, Carolina Power & Light Company (CP&L) plans to perform inspections during the Brunswick-1 Reload 5 outage, currently scheduled to begin on January 31,1987. The scope of the inspection is divided into three categories: (1) unrepaired austenitic stainless steel welds, (2) IE Notice 84-41 inconel butter welds, and (3) existing weld overlay repairs. A discussion of each category is included in the following section.

t l

f DISCUSSION Unrepaired Austenitic Stainless Steel Welds The Brunswick-1 Reload 5 inspection program will include ultrasonic testing (UT) of the susceptible Class I austenitic stainless steel welds which have not been overlayed.

l Table i provides a listing of these welds. This inspection scope meets the requirements of Generic Letter 84-11 and the requirements specified in the Safety Evaluation Report, dated July 17, 1986, regarding the Brunswick-1 Reload 4 IGSCC inspection program.

The personnel performing the IGSCC inspections will be qualified in accordance with the.

EPRI/B4 ROG/NRC requirements. The Company plans to smooth weld crowns as required and to use the automated GE SMART UT system for inspections where physical clearances allow.

IE Notice 84-41 Inconel Butter Welds IE Notice 84-41 describes cracking found in inconel butter welds of reactor pressure vessel (RPV) nozzles at Pilgrim-1. In response to this notice, CP&L inspected the Brunswick-1 inconel butter welds which are 4 inches or greater in diameter (excluding the 10-inch core spray nozzle welds) during outages conducted in 1984 and 1985. No indications were detected as a result of these inspections. Similar inspections performed on Brunswick-2 during the 1986 Reload 6 outage revealed small axial indications in each of the 28-inch suction nozzle to RPV welds.

8611100359 861031 PDR ADOCK 05000M 2 Q PDR 411 Fayetteville street e P O Box 1551

• Raleigh. N C. 27602

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Director of Nuclear Reactor Regulation

. NLS-86-401/ page 2 As a conservative response to the axial indications detected in the Brunswick-2 28-inch inconel butter welds, the Company plans to inspect the Brunswick-1 core spray inconel butter welds and to reinspect the 28-inch inconel butter welds. In addition, a sample of the 12-inch inconel butter welds will also be reinspected. These examinations will be performed by qualified personnel using EPRI qualified techniques. The GE SMART UT system will be utilized where physical clearances allow.

Existing Weld Overlay Repairs There are currently 32 weld overlay repairs on Brunswick-1. These are designed repairs; however, as-built dimensions show that many meet the standard guidance as proposed in the draf t of NUREG-0313 Revision 2. The length and surface finish of these repairs do not allow UT inspection using the EPRI qualified technique; therefore, reinspection will require lengthening and surface finishing prior to the UT examination. Ten of the repairs on Brunswick-1 were applied in 1983 and 1984. At the end of the current cycle, these repairs will have been in service for two fuel cycles. The remaining 22 repairs were applied during the 1985 Reload 4 outage and, as such, will have been in service for only one cycle.

CP&L plans to upgrade the ten repairs applied in 1983 and 1984 such that the inspections performed during the upcoming Brunswick-1 Reload 5 outage can be accomplished using the EPRI qualified UT technique. Upgrading these weld overlay repairs consists of adding length and thickness to the overlay, as required, and performing surface finishing. CP&L has endorsed a NUTECH analysis (see Attachment 1) which justifies continued operation of Brunswick-1 for an additional 18-month fuel cycle without upgrade or inspection of 21 of the 22 weld overlay repairs applied in 1985. As recommended by the report, the Company will upgrade and inspect weld 12"-B32-BR-3-3. In addition, the Company plans to upgrade and inspect as many of the remaining 21 repairs applied in 1985 as possible without impacting the outage critical path.

Additional Actions There are two remaining unrepaired susceptible welds in the 4-inch Class I return line piping of the Reactor Water Cleanup System. These welds will be replaced with nuclear grade materials during the Brunswick-1 Reload 5 outage.

The results of the inspections and a description of any corrective actions will be submitted prior to Brunswick-1 startup.

Please refer any questions to Mr. Stephen D. Floyd at (919) 836-6901.

Yours very truly,

? ' ussuw S. R. immerhan N anager Nuclear Licensing Section MAT /kts (5035 MAT)

Attachments I cc: Mr. W. H. Ruland (NRC-BNP)

Dr. 3. Nelson Grace (NRC-Ril)

Mr. E. Sylvester (NRC) l

TABLE 1 UNREPAIRED SUSCEPTIBLE AUSTENITIC STAINLESS STEEL JOINTS TO BE INSPECTED WINTER 1987/RF5 Weld Number Date of Last Inspection 4" B32 A-1 1984 4" B32 B-1 1984 4" B32 B-10 1984 12" B32 AR-A-1 1985 RF4 12" B32 AR-B-1 1985 RF4 12" B32 AR-C-1 1985 RF4 12" B32 AR-C-4 1985 RF4 12" B32 AR-D-1 1985 RF4 12" B32 AR-E-1 1985 RF4 12" B32 AR-E-4 1985 RF4 12" B32 BR-F-1 1985 RF4 12" B32 BR-F-3 1985 RF4 12" B32 BR-G-1 1985 RF4 12" B32 BR-H-1 1985 RF4 12" B32 BR-J-l 1985 RF4 12" B32 BR-3-4 1985 RF4 12" B32 BR-K-1 1985 RF4 20" Ell A-1 1985 RF4 20" Ell A-BC 1984 20" Eli A-2 1985 RF4 22" B32 AM-1 1985 RF4 22" B32 AM-2 1985 RF4 22" B32 AM-3 1985 RF4 22" B32 AM-3BCA 1984 22" B32 AM-3BCB 1984 22" B32 AM-4 1985 RF4 22" B32 AM-5 1985 RF4 22" B32 AM-5BCA 1984 22" BJ2 AM-5BCB 1984 22" B32 AM-6 1985 RF4 '

22" B32 BM-1 1985 RF4 22" B32 BM-1BCA 1984 22" B32 BM-1BCB 1984 22" B32 BM-2 1985 RF4 22" B32 BM-3 1985 RF4 22" B32 BM-3BC 1984 22" B32 BM-4 1984 22" B32 BM-4BC 1984 22" B32 BM-5 1985 RF4 (5035 MAT /kts)

TABLE 1 (continued) 24" Ell A-12 1985 RF4 24" Eli B-13 1985 RF4 28" B32 A-2 1985 RF4 28" B32 A-3 1985 RF4 28" B32 A-5 1985 RF4 28" B32 A-6 1985 RF4 28" B32 A-7 1985 RF4 28" B32 A-9 1985 RF4 28" B32 A-9BC 1984 28" B32 A-10 1985 RF4 28" B32 A-ll 1985 RF4 28" B32 A-12 1985 RF4 28" B32 A-12BC 1984 28" B32 A-13 1985 RF4 28" B32 A-15BC 1984 28" B32 A-16 1985 RF4 28" B32 A-17 1985 RF4 .

28" B32 A-18 1985 RF4 28" B32 B-2 1985 RF4 28" B32 B-3 1985 RF4 28" B32 B-5 1985 RF4 28" B32 B-6 1985 RF4 28" B32 B-7 1985 RF4 28" B32 B-9

. 1985 RF4 28" B32 B-9BC 1985 RF4 28" B32 B-10 1985 RF4 28" B32 B-ll 1985 RF4 28" B32 B-12 1985 RF4 28" B32 B-12BC 1984 28" B32 B-13 1985 RF4 28" B32 B-14 1985 RF4 28" B32 B-15 1985 RF4 28" B32 B-15BC 1984 28" B32 B-16 1985 RF4 28" B32 B-17 1985 RF4 28" B32 B-18 1985 RF4 (5035 MAT /kts)

ATTACHMENT 1' TO SERIAL NLS-86-401 (5035 MAT /bme )