ML18004A396
| ML18004A396 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 07/31/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NLS-86-282, NUDOCS 8608070247 | |
| Download: ML18004A396 (4) | |
Text
REQULAT INFORMATION DISTRIBUTIO STEN (RIDB)
ACCESSION NBR: S608070247 DOC. DATE: 86/07/31 NOTARIZED-NO DOCKET I FACIh': 50-400 Sheav on Harv is Nucleav Power Planti Unit ii Carolina 05000400 AUTH. NANE AUTHOR AFFILIATION ZII'1NERNANiS. R.
Carolina Power 5 Light Co.
REC IP. MANE RECIPIENT AFFILIATION DENTONp H. R.
Office of Nuclear Reactor Regulationi Divectov'post 85ii25
SUBJECT:
Submits addL info re conformance to iOCFR50. 6i. "Pressuri zed Thermal Shock. " Bouv ce of copper Cr nickel values in FBAR Table '5. 3. i-6 contained in certified test v'ept supplied bg vessel fabricator> (Chicago Bridge 8c Iron).
DISTRIBUTION CODE:
BCOID 'OPIES RECEIVED: LTR g ENCL +
SIZE:
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 0 Related Corv espondence NOTES: Applicatxon fov permit v enewal Piled.
05000400 RECIpIENT ID CODE/NANE pWR-A EB pWR-A FOB PMR-A PD2 PD PWR-A PBB INTERNAL: ADN/LFNB IE FILE IE/DQAVT/GAB 2i NRR PWR-B ADTB NRR/DHFT/NTB RQN2 EXTERNAL BNL(ANDTS ONLY)
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REC IP IENT ID CODE/MANE PWR-A EICSB PWR-A PD2 L*
BUCKLEY>B Oi PWR-A RSB ELD/HDBi IE/DEPER/EPB 36 NRR BWR ADTS NRR ROE'. L 04 RN/DDANI/NI8 DNB/DBS (ANDTS)
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- CSQ9, Carolina Power & Light Company JN. 31 Iggg SERIAL: NLS-86-282 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 PRESSURIZED THERMALSHOCK
Dear Mr. Denton:
Carolina Power k Light Company hereby provides additional information regarding conformance to 10 CFR 50.61, Pressurized Thermal Shock.
1.
The source of the copper and nickel values in FSAR Table 5.3.1-6 is the Certified Test Report supplied by the vessel fabricator (CBI Chicago Bridge k Iron) and documented as part of the Materials Certification Report.
H 2.
The values reported on the Certified Test Report were obtained from samples of the actual beltline material.
Plates:
Amounts of residual elements in the beltline plate were measured from samples removed from actual beltline plates.
Samples were prepared using the same heat, lot, and flux as the materials used in the vessel welds.
The above information willbe included in an FSAR amendment after fuel loading at SHNPP. If you have any questions on this subject, please contact Mr. 3ames D.
Kloosterman at (919) 836-8055.
Yours very truly, 3DK/pgp (0030 JDK) cc:
Mr. B. C. Buckley (iNRC)i Mr. B. Elliot (NRC)i Mr. G. F. Maxwell'NRC.-SHNPP)'.
Dr. 3. Nelson Graze (5RC-.RII)'ake Counav public E.ihaaar 8608070247 860731
'DR ADOCK 05000400 PDR S.. Zi erman ager Nuclear Licensing Section 411 Fayettevilte Street o P. O. Box 1551 e Raleigh, N. C, 27602 roooo 0
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