L-77-200, Forwarding Final Inservice Inspection Reports

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Forwarding Final Inservice Inspection Reports
ML18227D481
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 07/01/1977
From: Pearson J, Robert E. Uhrig
Florida Power & Light Co
To: Stello V
Office of Nuclear Reactor Regulation
References
L-77-200
Download: ML18227D481 (4)


Text

5.S.

NUCLEAR REGULATORYI'ISSION NRC ppaM 195 l2 78.

NRC DISTRISUTION FOR PART 50 DOCKET MATERIAL DOCKET NUMBE FILE NUMBER ETTE R ABORIGINAL WICOPY QNOTORIZED JRVNCLASSIFIED

'Mr. Victor Stello PROP INPUT FORM FROM:

FPL Miami, Florida 33101 Robert E. Uhrig DATE OF DOCUMENT 07-01-77 DATE RECEIVED 07-07-77 NUMBER OF COPIES RECEIVED DESCRIPTION 1 page ENCLOSURE Consists of Final Inservice Inspectio Report.for Turkey Point Units 3

G 4...

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'PLANT NAME-. TURKEY POINT UNITS 3 G 4 lcm 07-07-77

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FOR ACTION/INFORII/IATION EVIVIRHNMENTAL ECT MANAGER:

TCENSING ASSXSTAVLT:

ASSIGNED AD:

Vo MOORE LTR BRANCH CHIEF:

PROJECT i~AGER:

LICENSING ASSISTANT:

INTERNAL0 STFMS SAFETY HEINEMAN EDER B~ HARLESS ISTRI BUTION PLANT SYSTEMS TEDESCO BENAROYA SITE SAFETY IEc ENVIRON ANALYSIS DENTON IEc LLLLER ENGINEERING IPPOLITO OPERATING REACTORS ENVIRO TECH ERNST BALLARD OUNGBLOOD VA TOCZY CHECK AT I LTZMAN T ERG E

BAER BUTLER G IME GAMMILL

( 2 SITE ANALYSIS VOLLMER BUNCH J ~ COLLINS TIC

~

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EXTERNAL OISTR IBUTION NSIC CONTROL NUMBER REG IV J

HAiICHETT 16 CYS ACRS SEiVT CAT GO Y NRC FORM 195 I2-78)

%gIIfatory Docf(et FiTa P.O. BOX 013100, MIAMI, FL 33101 gpss I/i~

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FLORIDAPOWER & LIGHTCOMPANY July 1, 1977 Z,-77-200 Director of Nuclear Reactor Regulation Attention:

Mr. Victor Stello, Director Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Stello:

Re:

Turkey Point Units 3 and 4

Docket Nos.

50-250 and 50-251 Inservice Ins ection Reports r

Inservice examinations of selected components within the main Reactor Coolant System pressure boundary were performed during the Spring 1976 refueling outage for Unit 4 and the Pall 1976 refueling outage for Unit 3-Components were selected in accord-ance with the Technical Specifications and the 1970 Edition, includ'ng the Winter'1970 Addenda, o

Section XI of the ASME Boiler and Pressure Vessel

Code, "Rules for Inservice Inspection of Nuclear Reactor Coolant Systems".

In accordance with Technical Specification 6.9.3.a, 20 copies of the final Inservice Inspection Reports are forwarded, herein for your'nformation.

Very truly yours, Pobert E. Unrig Vice President REU/HAS/cpc Attachments (2) cc:

Mr. Norman C. Moseley, Region II Pobert Lowenste'n, Esquire PEOPLE... SERVING PEOPLE

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