ML20210A769

Leakage Reduction Program Summary Rept for Control Room Drive Sys-(C1100),Fermi Unit 2

ML20210A769
Person / Time
Site:	Fermi
Issue date:	02/03/1987
From:	Agosti F DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM C1100-86-01, C1100-86-1, VP-NO-87-0017, VP-NO-87-17, NUDOCS 8702090009
Download: ML20210A769 (4)

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LEMUCE REDUCTIN PIOGRAM SMGM RERRT POR CDNFR[L RCD DRIVE SYSITM - (C1100)

Df?PROII' EDICON CXXfPMN FETCII-2 IUIER PLMTP i

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l REVRT 10.

_ C1100-86-01

,Date: J-3-f 7 Propiral Dy ISI Ifograma Su{A5tvisor

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Appro/od Dy Dato: 1 J k7 m

Plant IhnacJor B702090009 870203 PDR ADOCK 05000341 I'

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LEAKNIE REUCPION PROGRN4 REIORT FOR OMMI, IG DRIVE VGDE QNmm, SYS1H4 (C11-00)

_INm3XKTION: Both the Fermi-2 Technical Specifications, piragraph 6.8.4.a.2, and the Fermi-2 FSAR, Section H.III.D.1.1, require that leakage fran systans outside prinnry containment that could or would contain highly radioactive fluids, be reduced and maintained to as-lov-as-practical levels. To denonstrate the leak tight integrity of the Control Rod Drive Volume Control Syston, a systan leakage test is corductal once per reactor refueling (apprecinntely onco every 18 nonths). This report is for the initial leakage test.

REPHIEN3S:

1)

Dwg. Ib. 6M721-5703-1, " Control Rod Drive Syston - Functional Operating Sketch".

2)

Dwg. Ib. 6M721-5703-2, " Control Rod Drive Scram Discharge Syston -

Functional Operating Sketch".

3)

Proccduro tb. 43.106.02, " Control Rod Drivo Hydraulic Leakago Ibnitoring Test". (A copy of this proccdure is on filo at the plant).

4)

Procedure Ib. 43.401.355, " Local Leakage Pato Testing for Penetration X-37 & X-38".

(cantrol Rod Drive, a copy of this procalure is on filo at the plant).

_TESP DESCRIPTIN: The Control Rod Drive Syston was testal by tsvo separato proccxiures. The first was performed July 21, 1986 urder procedure 43.301.355. During this surveillance the test volume fran the C11-F127 (outlet scram valves) to C11-F180 ard F181 (outboard containment isolation valves), including the Ibrth and South scram discharuc headers (6M721-5703-2), was pressurized to Pa (56.5 psig). Leakago was measural by the arount of nikcup required to keep the test volume pressurized at Pa.

On Octci>cr 15, 1986 with the vessel at ratcri pressure ard tamorature the socord survoillance was performed. The CRD Systen was inspected fran cach Drywell Containment Penetration to the !!ydraulica control units (6tf/21-5703-1), leakago was rnoasured and recorded.

TERP SLM9RI: On thy 22, 1986, a LLRT test was perfonned on C11-F180 ard C11-F101. The leakage of thcGo valves failed the acceptanco requiramnts within the LLRT proceduro 1.0. the leakago was greater than the allaeabic 5.00 SCFl!. thintance was perfomxi, the valves were rotestcil ard passed LLRT testing on July 21, 1986 with a leakago of 1.65 ECFl!.

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LEAKN3E REDUCTION PROGRAM REIORT FOR G3ffML MD DRIVE VEIDE QNmCL SYSNM - (Cll-00)

On October 15, 1986, during Plant operation the Control Rod Drive Volume Control was inspected for leakage while the reactor was at normal operating pressure.

Test Results Sucmary: Corrective maintenance yielded a not result of:

TEST # 1 LLRT TESP 43.401.355 As Found Leakage Leakage RcIluced By As Left Leakage Maintenance Activity

>40 SCFH

>40 SCFH 1.82 SCFH TESP # 2 LFMJGE REDUCTION ' ESP 43.106.02 Examination Itcm Leakage Annunt Ibrth HCU bank valves and flanges 62 drops / min South HCU bank valves and flanges 127 drops / min ACCEPTANCE CRITERIA: The general leakage criteria to be appli(xl during the first fuel cycle as the basis for instituting corrcctive action in the form s

of corrective maintenance shall be 5.0 SCFH for LLRT testing and 30 ml (900 drops)/ min total leakage for both Ibrth arrl South HCU banks.

Per the EF-2 FSAR, this leakage criteria will be further evaluated at the end of the first refueling cycle to determine the long range leakage rcduction program criteria. This will allcw experience gained during the initial fuel cycle to be factorcri into the long range criteria.

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Frank E. Agostl Ves Pressoant Nuclear Operations s

Detroit re-a 6400 North Disse Highway ISOn Newport.Mechigari 48166

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operatfons Nuclear (313) 586-4150 Feoruary 4, 1987-VP-NO-87-0017.'

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U. S. Nuclear RegulatCry Consnission Attn: Document Control Desk Washington, D. C. 20555

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References:

1) Fermi.2 NIC DockdC No.-50-341' NIC LicensoJNo.- tW-43 K

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2) h*JREG.0737, Ittso f1I.D.l.1

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Fermi 2 Final Safety

+ Analysis Report, Appendix H, 7., Section H.III.D.l.1 ~

4) sFermi 2 'li!chnical fpecifications, Section 6.8.4.A

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Subject:

Icakage Reduction 'itst Results Control Roi Drive System !C11-Om Ehclosed is the Ieekage Reduction program Summary Report for the Control Bod orive System (Cll-00). This is n partial submittal ad Detroit Edison has cmuitted to '

submit reports as (hey are conpletw1.

If you have any quec'tions, please contact Md. Girija N-Shukla at (313) 586-4672.

sincerely, C3-t'{ E f Enclosure cc: Mr. E. Greenman Mr. W. G. Rogers Mr. J. J. Gtefano l

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