ML20209H708
| ML20209H708 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/01/1985 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| GL-84-11, NLS-85-390, NUDOCS 8511110199 | |
| Download: ML20209H708 (4) | |
Text
,,
CD&L Carolina Power & Light Company SERIAL: NLS-85-390 NOV 0 11985 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324 / LICENSE NO. DPR-62 1
IGSCC INSPECTIONS
Dear Mr. Vassallo:
Generic Letter 84-11 initiated a reinspection program for piping susceptible to intergranular. stress corrosion cracking (IGSCC). In accordance with this requirement, Carolina Power & Light Company (CP&L) plans to perform the following inspections and mitigative actions during the Brunswick-2 Reload 6' outage, scheduled to begin on December 1,1985:
1.
The isolable portion of Class I 6-inch reactor water cleanup (RWCU) system piping will be replaced with nuclear grade materials. This will eliminate three weld overlay repairs on the RWCU system. The primary containment penetration will be modified to eliminate the inaccessible weld of the original flued head penetration design.
2.
Five weld overlay repairs will be reinspected by ultrasonic testing (UT). The weld overlays to be inspected are listed in Table 1.
3.
The 11 welds listed in Table 2 will be reinspected and reevaluated. These welds contain [GSCC indications but are not overlayed.
4.
Induction lieating Stress improvement (IHSI) will be performed on selected recirculation system and residual heat removal (RHR) system weld joints. Industry accepted methods will be utilized and the welds will be UT inspected af ter treatment. A sample of welds will be UT inspected prior to IHSI. Joint selection for IHSI will be based on accessibility, geometry, and IGSCC susceptibility.
5.
The IGSCC inspections will be performed in accordance with the requirements of Generic Letter 84-11. Personnel performing IGSCC inspections will be requalified in accordance with EPRI requirements. The Company currently plans to use the automated GE SMART UT system on inspections where physical clearances allow.
8511110199 851101 PDR ADOCK 05000324 A
O PDR
'[
u f
411 Fayetteville street a P. O. Box 15$1
- Raleig" N. C 27602
-m
^
- Mr. D, B,. Vassallo NLS-85-390 / Page 2 The results.of the inspections, the specific scope of the IHSI program, and a description -
of any further corrective actions will be submitted prior to Brunswick-2 startup.
Please refer any' questions to Mr. Sherwood R. Zimmerman at (919) 836-6242.
Yours very truly h
$$l A.-B. Cutter - Vice Prest ent Nuclear Engineering & Licensing ABC/ MAT /mf (2081 MAT) cc: ~
Mr. W.11. Ruland (NRC-BNP)
Dr. J. Nelson Grace (NRC-Ril)
Mr. M. Grotenhuis (NRC) t i
i f'
TABLE 1 WELD OVERLAYS TO BE INSPECTED DURING BRUNSWICK-2 DECEMBER 1985 OUTAGE 2-B32-12"-BR-G-4 SS Pipe to SS Safe-End 2-B32-12"-BR-3-2 SS Pipe to SS Elbow 2-B32-12"-BR-3-3 SS Elbow to SS Pipe 2-B32-12"-BR-K-2 SS Pipe to SS Elbow 2-B 32-12"-BR-K-3 SS Elbow to SS Pipe e
I (2081 MAT /mf)
c TABLE 2 UNREPAIRED WELD JOINTS WITH IGSCC INDICATIONS TO BE INSPECTED DURING THE BRUNSWICK-2 DECEMBER 1985 OUTAGE 2-B32-28"-A-4 SS Elbow to SS Pipe 2-B32-28"-A-8 SS Elbow to SS Valve 2-B32-28"-A-13 SS Pipe to SS Valve
~
2-B32-28"-A-14 SS Valve to SS Elbow 2-B 32-28"-B-3 SS Pipe to SS Elbow 2-B32-28"-B-4 SS Elbow to SS Pipe 2-B32-28"-B-5 SS Pipe to SS Tee 2-Bi2-28"-B-9 SS Valve to SS Pipe 2-B32-22"-AM-5 SS Pipe to SS Cross 2-B32-22"-AM-1 SS Cap to SS Pipe 2-E11-RHR-20"-A-SUCT-2 SS Pipe to CS Valve
- \\
i s
s s4
,v
\\
(208tMAT/mt)
.