ML19319D237
| ML19319D237 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/09/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130863 | |
| Download: ML19319D237 (2) | |
Text
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NRC FO" M 195 U.S. NUCLEAR REGULATORY f MISSION DOC KET NUMS E R S0-302 n.: u NRC. DISTRIBUTION FOR PART 50 DOCKET MATERIAL TO:J. STOLZ FROMFLORDIA POWER CORP.
DATE OF DOCUMENT ST. PETERSBURG, FLORDIA 12-9-76 J.T. RODGERS DATE RECElvEo 12-10-76 OLETTER ONOTORIZED PRCP~
INPUT FORM NUMBER OF COPIES RECElVED DORIGIN AL
$ UNCLASSIFIED OCOPY 40 DESCRIPTION ENCLOSURE LTR. TRANS THE FOLLOWING.......
REACTOR CONTAINMENT BUILDING PREOPERATIONAL INTEGRATED LEAK RATE TEST REPORT GAI 1927...
( 1 SIGNED CY. RECEIVED)
)
( 41 PAGES)
ACKNOWLEDGED DO NOT REMOVE l
PLANT HAME:
CRYSTAL RIVER S66
/W SAFETY FOR ACTION /INFORMATION rNvTun SAB 12-10-76 11SSIGNED AD:
ARRTcMPn AM.
/ BRANCH CHIEFr STOLZ unAMcu nnTrr.
PROJECT MANAGER:
PROJECT MANAGER:
/ LIC. ASST. :
MLM LIC. ASST. :
INTERNAL DISTRIBUTION
/ MEG FILD SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &
i
/ NRC PDR HEINEMAN TEDESCO ENVIRO ANAINSTE t
/ I&E m SCHROEDER BENAROYA DENTON & M117.T.vR OELD T.ATNAR GOSSICK & STAFF ENGINEERING IPPOLITO ENVIRO TECH.
/ MIPC_
MACARRY KIRKWOOD ERNST CASE KNIGHT BALLARD
/ HANAUER SIHWEIL OPERATING REACTORS SPANGLER HARLESS PAWLICKI STELLO SITE TECH.
PROJECT MANAGEMENT REACTOR SAFETY OPERATING TECH.
CAMMILL BOYD ROSS EISENHUT STEPP
_ P. COLLINS NOVAK SHA0 HULMAN HOUSTON ROSZTOCZY BAER PETERSON CHECK BITTLER SITE ANALYSIS MELTZ GRIMES VOLLMER l
HELTEMES AT & I BUNCH SKOVHOLT SALTZMAN J. COLLINS RUTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER
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N Wa'shington, D. C. 20555
Subject:
Crystal River Unit #3 Docket 50-302
Dear Mr. Stolz:
During the period of November 5 and 6,1976, the Crystal River Unit #3 reactor containment building was subjected to a pre-operational integrated leak rate, test. The purpose was to demonstrate an acceptable building leak rate at 49.6.Psig. The measured leakage was found to be 0.057% by weight per day which is well below the allowed 0.187% per day at 49.6 Psig.
We are today supplying to you 40 copies of our final ILRT report No. 1927 dated December 10, 1976 titled " Pre-operational Integrated Leak Rate Test of the Reactor Containment Building - Crystal River Unit 3" prepared by 7
Gilbert / Commonwealth.
This test was witnessed by NRC I&E Atlanta personnel and the preliminary
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results reviewed with their personnel.
Should you have questions or require anything further, please advise.
Very truly yours, 9
J.
. Rodgers JTR:ejv Assistant Vice President cc:
Mr. Norman C. Moseley Director, Region II I&E Atlanta, Ga.
F j 't ^ RQ 4
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General Office 32o1 inirty-fourin street soutn. P.O. Box,p 14042, st. Petersburg. Florida 33733 813--866-5151
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