ML18017B697
| ML18017B697 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/18/1982 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18017B698 | List: |
| References | |
| NUDOCS 8205210266 | |
| Download: ML18017B697 (4) | |
Text
L REGULATO INFORMATION DISTRIBUTION TEM (RIDS)
AOCCSSION NUR:8?05210266 DOC ~ DATE; 82/05/18 NOTARIZED; NO FACIL:50-400 Shearon Harris Nuclear Power Plant~
Unit 1< Carolina 50"401 Shearon Harris Nuclear Power Plant~
Uni,t 2~ Carolina AUTH BYNAME AUTHOR AFFILIATION HONEzP AN ~
Carolina Power 8 Light Co ~
>>REC IP, NAME RECIPIENT AFFILIATION DENlONa H ~ R e Office of Nuclear Reactor Regulationg Director DOCKET 05000<00 05000001 DISTRIBUTION CODE:
B001S COPIES RECEIVEDtLTR,J ENCL TITLE: PSAR/FSAR AMDTS and Related Correspondence NOTES: PHH SZ
SUBJECT:
For wards Revision 0 to Procedure;80A5035r "Reactor Pressure Vessel Pr eservice Insp Program Plan,"
SIZE J Q)g RECIPIENT ID CODE/NAME A/D LICENSNG LIC BR 03 LA INTERNAL'LD/HDS1 IE/DEP EPDS 35 MPA NRR/DE/EQB 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SAB 2Q NRR/DHFS/HFEBOO NRR/DHFS/OLB 3g NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DS I/ETSB 12 NRR/DS I/PSB 19 B
23 EG FILE 00 EXTERNAL: ACRS FEMA-REP DIV 39 NRC PDR 0?
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'I gg)Qrt, Carolina Power & Light Company HAY 18 1992 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D.C.
20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS.
1 AND 2 DOCKET NOS. 50-400 AND 50-401 REACTOR VESSEL PRESERVICE INSPECTION PROGRAM
Dear Mr. Denton:
As committed to in Section,5.2.4 of the Final Safety Analysis Report (FSAR), Carolina Power
& Light Company (CP&L) submits five copies of the Reactor Vessel Preservice Inspection Program for the Shearon Harris Nuclear Power Plant, Unit 1.
This program has been developed in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition with addenda through Winter 1981.
This edition of Section XI was selected to provide baseline data as comparable as possible to that which will be taken during subsequent Inservice Inspections.
CP&L's position with respect to Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations" will be submitted with amendment 3 of the SHNPP FSAR which is scheduled for submittal in June, 1982.
This Reactor Vessel Preservice Inspection Program is applicable for all preservice examinations of reactor vessel components which are scheduled to begin with the mechanized inspection of reactor vessel welds in the last quarter of 1982.
CP&L will advise you of the exact date for the star t of examinations at least fifteen (15) days prior to their start.
As required additions or changes are identified, CP&L will submit the necessary information to you.
If you have any questions concerning this inspection program, please contact our staff.
Yours very truly, goo(
5 JHE/lr (n-55)
Enclosures P.
W. Howe Vice President Technical Services cc:
Mr. E. A. Licitra (NRC)
Mr. J.
P. O'Reilly (NRC-I&E)
<14~"~ """,.;lite Street o P, O. Box 1551
~ Raleigh, N. C. 27602 saosaioaa6 8205ia l.
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