ML20214J399

Leakage Reduction Program Summary Rept for RCIC Sys (E51-00)

ML20214J399
Person / Time
Site:	Fermi
Issue date:	03/12/1987
From:	Lenart D, Shiffel B DETROIT EDISON CO.
To:
Shared Package
ML20214J375	List: ML20214J381 ML20214J399 ML20214J415 NRC-87-0006, Forwards Three Leakage Reduction Program Summary Repts for Hpci,Rcic & Standby Gas Filter Sys.Addl Repts Will Be Submitted Upon Completion
References
E5100-87-01, E5100-87-1, NUDOCS 8705280037
Download: ML20214J399 (3)

Text

INWE REDUCfIOli PROGPA!! SLI21ARI REIORf EUR REACIOR CDRE ISOTATIOli C)OLIlU SYSfDI (E51-00)

DCTROIT EDISO!I CJllPAIE FERII-2 IUJER PLA17f REIORT ID. - E5100-87-01 1

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1 Prepared By: [N M Date: 8-f-8'[

'87Progra:ff Suprvisor ApprovM BY:

, Plant !lanager Date:/ 4, ff Dk kh0h7 870522

', P 05000341 PDR l

LERKAGE REDUCTION PROGRAM REPORP FOR 1

REAC' LOR CORE IS0[ATION COOLING SYSTEM (541-00)

INIMDUCTION: Both the Fermi 2 Technical Specifications, paragraph 6.8.4.a.2,  ;

and the Fermi-2 UFSAR Section 5.2.7, require that leakage from systens outside primary containment that could or would contain

! highly radioactive fluids, be reduced and maintained to

] as-low-as-practical levels. .To demonstrate the leak tight integrity of the Reactor Core Isolation Cooling system, a

system leakage test is conducted once per reactor refueling l (approximately once every 18 months) .- This report is for the initial leakage test.

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REFEREEES: 1) Dwg. No. 6M721-5709-1, " Reactor Core Isolation Cooling System-Functional Operating Sketch."

i j 2) Plant Operations Manual 43.206.01, " Reactor Core Isolation Cooling System Leakage Monitoring Test." (A copy of this

procedure is on file at the plant) .

l 'ITsr DESCRIPTIONS: With the vessel at rated tenperature and pressure the

Reactor Core Isolation Cooling (BCIC) System was placed in the test flow mode, taking suction from the Condensate '

i Storage Tank. . While ICIC was in the test flow moder

l. punp, instrumentation and all piping outside containment l was walked down with all leakage noted and measured.

After the walkdown was coupleted, BCIC was placed in the standby mode and the Torus suction valve was opened following which time the Torus suction piping was i inspected and all discrepancies noted.

l TEST RESULTS: The ICIC Leakage Monitoring Test was completed I Decenber 23, 1986, and leakage was noted at the following  !

j points: '

i Component I. D. I4akage Area of Leakaae l

l E51-F013 45'ml/ min Packing Leak j E51-F046 10 drops / min Steam Leakoff Nipple i E51-F094h I drop / min Packing Area E51-F026 1 drop / min Packing Area After review of test data all leakage was accepted.

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Page 2 TEST.RESULTS SCM RRY: Total water leakage measured during the walk down was aEproximately 46 ml per min.

A03PM!CE CRITERIA: The general leakage criteria to be applied during the first fuel cycle as the basis for instituting corrective maintenance shall be 200 ml per min. This leakage criteria will be further evaluated at the end of the first refueling cycle to determine the long range leakage reduction program criteria. This will allow experience gained during the initial fuel cycle -to be factored into the long range criteria.

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