ML19289E900
| ML19289E900 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/22/1979 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905290370 | |
| Download: ML19289E900 (2) | |
Text
)
May 22, 1979 FILE: NG 3514(B)
SERIAL:
GD-79-1355 Office of Nuclear Reactor Regulation ATTENTION:
M". T. A. Ippolito, Chief Operating Reactors Branch No. 3 United States Nuclear Regulatory Commission Washington, D. C.
20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 SEISMIC ANALYSIS OF SAFETY-RELATED PIPING
Dear Mr. Ippolito:
On May 21, 1979, representatives of Carolina Power 6 Light met with the NRC staff to present results of the reanalysis of piping and supports conducted to date, and to discuss our schedule and priority for further reanalyses. During this meeting, CP&L offered several commitments with regard to schedules and re-analysis activities.
This letter formalizes the verbal commitment we made on May 21, 1979 stating that we would perform an inspection and comps.rison of "as built" conditions versus "as designed" and "as-analyzed" conditions for lines set forth in Attachments 2 and 3 of our letter of May 21, 1979. We will inspect those lines outside of containment as expeditiously as practical and will inspect lines inside containment at the next scheduled outage. Results of these inspections and comparisons will be submitted to the NRC for their evaluation.
This letter also documents statements made by CP&L at the meeting concerning the reanalysis of the BSEP 1 & 2 recirculation loops. We have written verification that GE reanalyzed the pipe and supports for the recirculation loop using the PISYS code, and all pipe and support loads are within allowable stresses. The support loads for the first ten lines reanalyzed by UE&C, (as identified in our April 24 and May 15, 1979 letters) are presently being evaluated by UE&C, and the results of these approximately 100 support loadings will be submitted to the NRC by Friday, May 25, 1979.
During the May 21 meeting, several documents were presented to the NRC.
Following is an identification for the docket of this material:
Sheets 15, 121, 122, 125, ano 237 of the main steam line problem, consisting of isometrics, computer input, output, and input definitions for UESC ADLPIPE-2.
Computer results of Problems 2A, 3A, and 5A of BNL-NUREG-21241-R2, Development of Solutions to Benchmark Piping Problems, Verification of UE&C-ADLPIPE 2 analysis.
2048
?39 gopt kl 05a90376' 3
~
t.
General Electric Record File B32-7, Books 1 & 2, BSEP Recirculation Analysis, PISYS computer code.
Our submittal on >by 2R will discuss the results of line verifications conducted by NRC I&E on May 18 & 19, 15/9 as well as results of support loadings on the first ten lines reanalyzed by UESC.
If you have any questions concerning this material, pL se contact our staff.
Yours very truly,
--.^
,t 'E f$.';<u,/k' (,,,
ExecutiveVicePreside\\
nt Power Supply DB/tl cc:
Mr. James P. O'Reilly Office of II.spection & Enforcement 2048
?4C
'