L-86-181, Forwards Final Core Support Barrel Insp Rept,Post-Cycle 6. Condition of Core Support Barrel Same as Found During post- Cycle 5 Insp.Barrel Acceptable for long-term Svc
| ML17216A526 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/25/1986 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | Thadani A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17216A527 | List: |
| References | |
| L-86-181, NUDOCS 8605090039 | |
| Download: ML17216A526 (4) | |
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C REQUL*TOROINFORNATION DIBTRIBUTIOI4 ~TEN (RIDE>
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ACCESSION NBR: 8605090039 DOC. DATE: 86/04725 NOTARIZED:
NO FACIL: 50-335 St.
Luci e Plant>
Unit ii Florida Power 8r Light Co.
AUTH. NANE AUTHOR AFFILIATION WOODY'. O.
Florida Power 8c Light Co.
RECIP. NANE RECIPlENT AFFILIATION THADANIiA. C.
PWR Prospect Directorate 8
DOCNET 0 05000335
SUBJECT:
Forwards "Final Core Support Barrel Insp Rept. Post-Cgcl
- 6. "
Condition of core support barrel same as found during post-Cgcle 5 insp. Barrel acceptable for long-term SVC.
OISTRIBUTIQN CODE:
A047O COPIES RECEIVED: t TR ENCL SIZE:
TITLE:
OR Submittal:
lnservlce Inspection/Testing NOTES:
RECIPIENT ID CODE/NANE PWR-8 EB SELLS> D INTERNAL: ADN/LFNB NRR BWR AOTS NRR PWR-A ADTS NRR PWR-8 ADTS
/EIB REQ FILE 04 COPIES LTTR ENCL 1
1 1
0 1
1 1
1 1
1 RECIP lENT ID CODE/NANE PWR-8 PDS PD 01 ELD/HDS2 NRR BWR EB NRR PWR-A EB NRR PWR-8 EB NRR/TANB RQN2 COPIES LTTR ENCL 5
5 0
1 1
1 1
1 1
EXTERNAL: 24X NRC PDR 02 LPDR NSIC 03 05 TOTAL NUt')BER OF COPIES REQUIRED:
LTTR 23 ENCL 21
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FLORIDAPOWER 5 LIGHTCOMPANY gag p 5 1888 L-86-181 Office of Nuclear Reactor Regulation Attention: Mr. Ashok C. Thadani, Director PWR Project Directorate
/78 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Thadani:
Re: St. Lucie Unit 1 Docket No. 50-335 Thermal Shield Recovery Program Final Core Su ort Barrel Ins ection Re ort (Post-C cle 6)
As part of the Thermal Shield Recovery Program for St. Lucie Unit 1, FPL letter L-80-29 of February 10, 1980 submitted a "Final Integrity and Stability of Internals Report" that supported return to power -for Cycle 6 operation.
In conformance with the inspection program described in Section 10.5.1 of that report, FPL performed a short-term core support barrel (CSB) inspection during the refueling outage following Cycle 6. A final report describing the results of that inspection is at tached.
The subject report concludes that the condition of the Unit I CSB is the same as the condition seen during the post-Cycle 5 baseline inspection; therefore the CSB is acceptable for continued long-term service.
The next CSB inspection will be performed in accordance with the revised second 10-year inservice inspection program.
Very truly yours, C. O. Woo Group Vice President Nuclear Energy COW/MAS/SAV:dee Attachment cc:
Dr. 3. Nelson Grace, USNRC, Region II Harold F. Reis, Esquire, Newman R Holtzinger PNS-LI-86-133 pgp g00~9 860425 860SQ
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