ML20207B608
| ML20207B608 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/27/1999 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | Keenan J CAROLINA POWER & LIGHT CO. |
| References | |
| GL-88-01, GL-88-1, GL-89-10, TAC-MA3450, TAC-MA3451, NUDOCS 9906020037 | |
| Download: ML20207B608 (5) | |
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May 27, 1999 Mr; J. S. Keenan, Vice President
' Carolina Power & Light Company Brunswick Steam Electric Plant -
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Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
i REVIEW OF INTERGRANULAR STRESS CORROSION CRACKING INSPECTION PLAN FOR REACTOR WATER CLEANUP SYSTEM i
PIPING WELDS OUTBOARD OF THE SECOND CONTAINMENT ISOLATION VALVE FOR BRUNSWICK STEAM ELECTRIC PLANT,
~ UNIT NOSJ1 AND 2 (TAC NOS. MA3450 AND MA3451) i
Dear Mr. Keenan:
In a [[letter::BSEP-98-0159, Requests NRC Concurrence W/Plans to Remove Piping Welds Outboard of Second Containment Isolation Valve in RWC Sys of Plant,From Insp Extent & Frequency Outlined in GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless..|letter dated August 20,1998]], Carolina Power and Light Company (CP&L, the licensee)
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requested NRC approval for eliminating the intergranular stress corrosion cracking (IGSCC)
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. Inspection of the Reactor Water Cleanup (RWCU) system piping welds outboard of the second
' containment isolation valves at Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The 1,
subject portion of the RWCU piping can be isolated from the containment by closing the isolation valves. In accordance with Supplement 1 to Generic Letter (GL) 88-01, the inspection of these I
welds may be reduced or eliminated when the actions associated with GL 89-10 on motor-operated containment isolation valves are completed by the licensee.
The NRC staff has completed its review of this request. The staff position regarding the acceptable inspection schedules for the subject portion of RWCU system piping welds is provided in the Enclosure. To qualify for a reduction of the augmented IGSCC inspection in i
Schedule A, the subject piping system should meet all three criteria (delineated in the Enclosure) or meet criteria (1) when the subject piping is made of IGSCC-resistant material.
The licensee stated that, for BSEP Units 1 and 2, the RWCU system piping outboard of the second containment isolation valves have been replaced with low carbon wrought austenitic stainless' steel material in accordance with the recommendations outlined in NUREG-0313, Revision 2. The low carbon stainless steel is resistant to IGSCC. ' The details of the subject piping replacement for BSEP, Units 1 and 2, were provided in the licensee's letters dated
. January 17,1989, and February 21,1990, respectively.
The NRC staff has reviewed the licensee's GL 89-10 actions or scheduled actions pertaining to i
those RWCU containment isolation valves ( Unit 1: 1-G31-F001 and 1-G31-F004; Unit 2:
2-31-F001 and 2-G31-F004). These isolation valves are Anchor / Darling double-disc gate valvesc The licensee has upgraded the valves 1-G31-F001 and 1-G31-F004 for BSEP, Unit 1, by installing larger capacity motors (25 foot-pounds). The licensee will complete similar upgrade of the 2-G31-F001 and 2-G31-F004 valves for BSEP, Unit 2, prior to start-up from refueling outage 13 (B214R1). Based on the information provided by the licensee and the planned 9906020037 990527 l.
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J.S.Keenan May 27, 1999 modification, the staff concluded that the licensee has met the intent of GL 89-10 for the RWCU motor-operated containment isolation valves of 1-G31-F001,1-G31-F004,2-G31-F001 and i
2-G31-F004 in verifying their' design-basis capability.
Based on the above, the staff finds that the RWCU system piping outboard of the second containment isolation valves at BSEP, Units 1 and 2, meets the staff criteria of Schedule A as delineated in the Enclosure. Therefore, the staff concludes that the licensee's proposal to eliminate the augmented inspection per GL 88-01 of the subject portion of RWCU piping at
.BSEP, Units 1 and ~2, is acceptable.
Sincerely, Original signed by:
Allen G. Hansen, Project Manager, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosure:
As stated cc: See next page DISTRIBUTION:
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modification, the staff concluded that the licensee has met the intent of GL 89-10 for the RWCU motor-operated containment isolation valves of 1-G31-F001,1-G31-F004,2-G31-F001 and 2-G31-F004 in verifying their design-basis capability.
Based on the above, the staff finds that the RWCU system piping outboard of the second containment isolation valves at BSEP, Units 1 and 2, meets the staff criteria of Schedule A as delineated in the Enclosure. Therefore, the staff concludes that the licensee's proposal to eliminate the augmented inspection per GL 88-01 of the subject portion of RWCU piping at BSEP, Units 1 and 2, is acceptable.
Sincerely,
~
Allen G. Hansen, Project Manager, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
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Enclosure:
As stated cc: See next page L
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1 l
CRITERIA RELATED TO INSPECTION RE0VIREMENTS FOR RWCU PIPING WELDS OUTBOARD OF SECOND ISOLATION V t
(1)
Satisfactory completion of all Generic letter 89-10 required actions.
(2)
No IGSCC detected in RWCU piping welds inboard of the second isolatio valves (on-going GL 88-01 inspection).
i (3)
No IGSCC detected in RWCU piping welds outboard of the second isolatio valves after inspecting a minimum of 10% of the susceptible piping welds.
IGSCC INSPECTION SCHEDULE FOR RWCU PIPING WELOS OUTBOARD OF SECOND ISOLATION VALVES
- Insoection Criteria Schedule Extent of Insoection Schedule A
-Meeting Criteria (1), (2) and (3)
N0 IGSCC INSPECTION REQUIRED or
-Piping Made of Resistant Material and Meeting Criterion (1)
Schedule B -Meeting Criteria (1),
But Not Meeting Criteria (2) or (3) AT LEAST 2% OF THE WELDS OR 2 WELDS EVERY REFUELING OUTAGE, WHICHEVER SAMPLE IS LARGER.
Schedule C -Not Meeting Criterion (1)
AT LEAST 10% OF THE WELDS EVERY REFUELING OUTAGE
- If IG5CC was found during inspection, the sample expanston and methods of mitigation including replacement should be discussed with the staff.
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Mr. J. S. Keenan Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:
Mr. William D. Johnson Ms. Karen E. Long Vice President and Corporate Secretary Assistant Attomey General Carolina Power & Light Company State of North Carolina Post Office Box 1551 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Jerry W. Jones, Chairman Mr. Robert P. Gruber Brunswick County Board of Commissioners Executive Director Post Office Box 249 Public Staff-NCUC Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Resident inspector U.S. Nuclear Regulatory Commission 8470 River Road Director
. Southport, North Carolina 28461 Site Operations Brunswick Steam Electric Plant Mr. John H.' O'Neill, Jr.
Post Office Box 10429 Shaw, Pittman, Potts & Trowbridge Southport, North Carolina 28461 2300 N Street, NW.
Washington, DC 20037-1128
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Mr. William H. Crowe, Mayor City of Southport Mr. Mel Fry, Director 201 East Moore Street Division of Radiation Protection Southport, North Carolina 28461 N.C. Department of Environment and Natural Resources Mr. Dan E. Summers 3825 Barrett Dr.
Emergency Management Coordinator Raleigh, North Carolina 27609-7721 New Hanover County Department of Emergency Management Mr. J. J. Lyssh Post Office Box 1525 Plant Manager Wilmington, North Carolina 28402
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Carolina Power & Light Company Brunswick Steam Electric Plant -
Mr. Terry C. Morton Post Office Box 10429 Manager Southport, North Carolina 28461 Performance Evaluation and Regulatory Affairs CPB 9 Public Service Commission Carolina Power & Light Company State of South Carolina Post Office Box 1551 Post Office Drawer 11649 Raleigh, North Carolina 27602-1551 i
Columbia, South Carolina 29211 Mr. K. R. Jury Manager-Regulatory Affairs Carolina Power & Light Company Post Office Box 10429 Southport, NC 28461-0429 Lt.