ML18019A557
| ML18019A557 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 01/27/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18019A558 | List: |
| References | |
| NLS-86-010, NLS-86-10, NUDOCS 8602030189 | |
| Download: ML18019A557 (4) | |
Text
N Yg REGULATOR FORMATION DISTRIBUTION 8'[+EM (RIDS >
ACCESSION NBR: 8602030189 DOC. DATE: 86/Oi /27 NOTARIZED:
NO DOCKET 0 FACIL: 50-400 Shearon Harris Nuclear Power Planti Unit 1I Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ZIMMERMANiS. R.
Carolina Poeer 8r Light Co.
RECIP. NAME RECIPIENT AFFILIATION DENTONI H. R.
Office of Nuclear Reactor Regulationi Director (post 851125
~a~
SUBJECT:
Forwards "Predicted behavior o+ Containment Bldg During Structural lntegritg Testi" in response to SER Confirmatory Item 8. Test scheduled for Mar 1986. Comparison of predicted vs actual results vill be submitted.
DISTRIBUTION CODE:
B001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8c Related Correspondence NOTES:
REC IP IENT ID CODE/NAME PWR-A ADTS PWR-A EB PWR-A FOB BUCKLEY'S B 01 PWR-A RSB INTERNAL: ACRS 41 ELD/HDS1 IE/DEPER/EPB 36 NRR BWR ADTS NRR PWR-B ADTS NRR/DHFT/HFIB NRRIQSBQ DIR 04 RN/DD*NI/NIB EXTERNAL: 24X DMB/DSS (AMDTS>
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1 RECIPIENT ID CODE/NAME PWR-A PD2 PD PWR-A EICSB PWR-A PD2 LA PWR-A PSB ADM/LFMB IE FILE IE/DGAVT/GAB 21 NRR PWR-A ADTS NRR ROE'. L NRR/DHFT/MTB NRR/DSRO/RRAB RQN2 BNL(AMDTS ONLY>
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@ME Carolina Power & Light Company
~37 SS SERIAL: NLS-86-010 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1 DOCKET,NO.50-000 CONTAINMENTBUILDINGULTIMATESTRENGTH CAPACITY
Dear Mr. Denton:
Carolina Power 2 Light Company (CPttrL) hereby submits additional information concerning the Shearon Harris Nuclear Power Plant (SHNPP) calculation of ultimate strength capacity of the Containment Building under uniform pressure.
This information is submitted in response to Safety Evaluation Report (SER) Confirmatory Item No. 8.
Attached are the test procedures and the expected analytical results for your review.
The expected analytical results predict what deformations will occur when the Containment Building is subjected to an internal pressure 1.15 times that of the design pressure.
The actual testing is currently scheduled for March 1986.
Upon completion of the testing, a comparison of the predicted versus actual results will be completed and submitted for NRC review.
If you have any questions concerning this subject or require additional information, please contact me.
Yours very truly, 3HE/mf (32133DK)
Attachments S.. Zi erman anager Nuclear Licensing Section CC:
Mr. B. C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. 3. Nelson Grace (NRC-RII)
Mr. S. B. Kim (NRC-SGEB)
Mr. Travis Payne (KUDZU)
Mr. Daniel F. Read (CHANGE/ELP)
Wake County Public Library Mr. Wells Eddleman Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)
Dr. 3. H. Carpenter (ASLB)
Mr. 3. L. Kelley (ASLB)
Mr. H. A. Cole SeOZOSO~89 Sh0127 PDR ADQCK 05000400l E
PDR 411 Fayettevilte Street
~ P. O. Box 1551 o Raleigh, N. C. 27602