ML19225B023
| ML19225B023 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/19/1979 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907230335 | |
| Download: ML19225B023 (4) | |
Text
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a UNITED STATES NUCLEAR REGULATORY COMMISSION y*
WASHINGTON, D. C M565 j
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- Docket No. 50-325/324 LICENSEE: Carolina Power & Light Company FACILITY: Brunswick Units Nos. 1 and 2
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 4, 1979 A meeting was held with representatives of Carolina Power and Light Company (CP&L), General Electric Company (GE) and United Enginears The and Constructors (UE&C) in Bethesda, Maryland on June 4,1979.
purpose of the meeting was to (1) provide a current status of CP&L's reanalyses of BSEP pipes and supports, (2) identify modifications yet to be completed, (3) verify that all lines inside containment are described accurately on iscaletrics,and (4) describe procedures to address deviations from as-built conditions.
A list of meeting attendees is enclosed along with a copy of the meeting agenda provided by CP&L.
CP&L docketed 21(iter dated June 4,1979 which provided the current status of BSEP sea.aic reanalysis of safety-related piping.
CP&L reported that 44 pipe supports on each unit required modifica-tion before returning to power operation. All redesign work had been completed and the schedule for completing the modifications was discussed.
CP&L reported that 510 points on the lines inside each drywell had been examined to verify that "as-built" conditions were reflected on Minor discrepancies had been found during this exam-the isometrics.
The licensee's program for evaluation of the pipe stress ination.
analysis for effects due to changes found in the "as-built" config-uration was discussed. A concern was identified relative to the lack of independent review and concurrence by a second pipe stress analyst.
This concern was resolved at the meeting.
At the conclusion of the meeting, CP&L agreed not to ceninence the approach to criticality on either unit until all pipe support modifi-cations for that unit had been completed.
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JUNE
'9 33 The NRC's safety evaluation addressing the response to IE Bulletin 79-07 and the return to power operation was issued on June 7, 1979.
7, MA = r; John N. Hannon, Project Manager Operating Reactors Branch #3 Division of Operating Reactors
Enclosures:
1.
Attendees 2.
Meeting Agenda
- 3' 413 09fr
JUNE
' 0 n79 ATTENDANCE NRC/CP&L on Brunswick 1 and 2 Seismic (Response to IE Bulletin 79-07)
CP&L P. W. Howe B. J. Furr D. B. Kincaid D. B. Waters D. L. Bensinger M. A. Conner UE&C J. Kreider B. Huselton G. Rigamonti GE N. Shirley NRC J. Hannon H. Wong K. Wichman J. Glynn A. Lee V. Nocnan*
T. Ippoli to*
- Part time 413 098
w CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT NRC MEETING JUNE O 1979 INTRODUCTION HOWE ANALYSIS CRITERIA KREIDER PIPE STRESS ANALYSIS - UPDATE KREIDER CATEGORY 1 CATEGORY 2 NRC SUGGESTED (CORIGX1.38) ALLOWANCE)
KREIDER AS-BUILT VERIFICATION PROGRAM PLANT VERIFICATION FURR REANALYSIS DECISION BASIS KREIDER/
RIGAF.0 Nil PIPE SUPPORT STATUS HOWE CONCLUS10NS HOWE
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