ML20101K310
| ML20101K310 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/21/1984 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| IEB-80-11, NLS-84-492, NUDOCS 8412310295 | |
| Download: ML20101K310 (2) | |
Text
O CP&L Carolina Power & Lignt Company SERIAL:
NLS-84-492 DEC21 W84 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 NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 MASONRY WALL DESIGN, IE BULLETIN 80-11
Dear Mr. Vassallo:
In our letter of April 27, 1984, Carolina Power & Light Company (CP&L) notified you that an additional 17 walls at the Brunswick Steam Electric Plant were being evaluated to determine whether or not upgrading of the walls would be required to meet code requirements for masonry walls. The purpose of this letter is to provide you with the results of that evaluation.
The evaluation of the walls discussed above consisted of a field inspection and mathematical analyses based on " Recommended Guidelines for the Reassessment of Safety-Related Concrete Masonry Walls" prepared by Owners and Engineering Firms Informal Group on Concrete Masonry Walls, October 6,1980.
Analyses were performed using the working stress design methods.
The field inspection determined that two walls previously labeled " Safety Related" should, in fact, be labeled "Nonsafety Related" as there is no safety-related equipment attached or in proximity to the walls.
These walls are Wall 2a in the Unit 1 Reactor Building, originally listed as one of ten walls committed to be upgraded in the aforementiont d submittal, and Wall 9a (one of 17 additional walls identified in the April 27, 1984 submittal) in the Diesel Generator Buildir....
Based on mathematical analysis. it was determined that the following walls 1 ave stresses within allowable limits (Attachment 1) described in the guideline" referenced above; therefore, no additional reinforcement is required:
Wall No.
Location 6d Control Building 8b Control Building 8e Diesel Generator Buildi1g 7a Diesel Generator Building 7e Diesel Generator Building 00f 4
o(p 411 Fayettevitle Street e P. O Box 1551
- Raieign N C 27602 4=
,1 8412310295 841221
%. c PDR ADOCK 05000324 G
Mr. D. B. Vassallo The remaining 11 walls will require additional reinforcement' to reduce
, stresses to be within the allowable limits indicated in Attachment 1.
These walls are:
Wall No.
Location 5a Diesel Generator Building Sb Diesel Generator Building Sc Diesel Generator Building 5d Diesel Generator Building 6a Diesel Generator Building 9e Diesel Generator Building 6b Control Building 6g Control Building 8a Control Building 8c Control Building 8d Control Building As committed in our April 27, 1984 letter, the design for the 9 walls which have been identified as needing fixes has beca completed.
In addition, CP&L expects to complete the fix designs for the 11 additional walls by July 1985.
In summary, following the re-evaluation, a total of 20 walls at Brunswick Units 1 and 2 will require modification. These 20 walls include 9 of the 10 walls discussed in our letter of April 27, 1984 as requiring modification and the 11 additional walls listed above.
Should you have any questions concerning this information, please contact Mr. S. R. Zimmerman at (919) 836-6242.
Your ry tru A. B. Cutter - Vice Pre dent Nuclear Engineering & Licensing JSD/ccc (894JSD)
Attachment cc:
Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-Rll)
Mr. M. Grotenhuis (NRC) 1
. -.