ML20096D475
| ML20096D475 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/31/1984 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20096D478 | List: |
| References | |
| NLS-84-375, NUDOCS 8409060087 | |
| Download: ML20096D475 (1) | |
Text
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r-CD&L Carolina Power & Light Company SERIAL: NLS-84-375 AUG 311984 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 9
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 MARK I CONTAIMiENT LONG-TERM PROGRAM ADDENDlH TO THE BRUNSWICK PLANT UNIQUE ANALYSIS REPORT
Dear Mr. Vassallo:
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In a_ letter dated August 1, 1984 (Serial No. NLS-84-309), Carolina Power &
Light Company informed you of our intentions of submitting an addendum to the Brunswick Plant Unique Analysis Report (PUAR). The enclosed addendum details the approach takca to resolve safety / relief valve (S/RV) second pop concerns at Brunswick. The evaluation shows that the S/RV discharge lines and supports, the torus internal structures, and the torus shell, as modified by the Mark I Containment Program, are acceptable for S/RV load cases C3.2 and C3.3.
The methodology employed in the new analyses is the same'as that reviewed by the NRC and approved in NUREG-0661.
Should you have any questions concerning this submittal, please contact Mr. John S. Dietrich at (919) 836-6154.
Yours very truly, Q
NWHWW S.
.Z erman ager Nuclear Licensing Section MAT /cce (487 MAT)
. Enclosure cc:
Mr. D. O. Myers (NRC-BNP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC)
Q
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B409060087 B40031 PDR ADOCK 05000324 p
PDR dit Fayetteville Street
- P. O. Box 1551
- Raleigh, N. C, 27602
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