ML19330B695

Submits Response to IE Bulletin 80-14 Degradation of BWR Scram Discharge Vol Capability. No Instances of Degradation of SDV Level Switch Identified During Review of Records

ML19330B695
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	07/31/1980
From:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
IEB-80-14, NUDOCS 8008050389
Download: ML19330B695 (3)

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u II 3ulletin :To SC-lk, dated June 12,1980, "regradaticn of 34a sera: Discharge Volu=e Capability" requested a review of certain aspects of the centrol red' drive syste: scran discharge volume related Oc operation and equi;=ent.

• I Sulletin 80-17, dated July 3,1960, " Failure of 76 of 135 Centrol Ecds to Ful'.y Inser Curing a Scra: at a 3'IR", has requested additicna' actions and reviews 2.'*".

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infor atic: =ay be found in Consumers ?cver Cc=pany's respenses to thesew '-e ins.

Censu=ers Power Cc=pany has cc=pleted the required actions as follows:

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Eeview plant records for instances of degradation of any 3DV level switch which was or =ay have been caused by a damaged er bent fica asss bly.

Identify the cause and corrective action for each instance.

Ees:cnse to Ite= 1

To instances of degradatica of any SLV level switch vere identified during the reviev cf plant records.

.. e. o Review plant recor.s for instances of degradatica of SCV vent and drain valve d

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previde the closure times required and t~J.ically observed for t

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't Mr James G Keppler 2

31g Rock Point Plant July 31, 1980 Tne purpose of autc=atic sers= du=p tank vent and drain valve closure at Big Rock Point is to li=it the' a=ount of water displaced from the reactor during a scra=. _ Specified closure. times are not currently required for these valves, but are being developed frc= surveillance test data in conjunction with ASMI Boiler and Pressure Vessel Code Section XI Valve Testing.

Closure times typically observed for the scrs= du=p tank vent and drain valves are approxi=ately h5 seconds when closed with the =anual handsvitch hS6 and approix=ately 17 seconds when automatically closed by a scra= signal.

The difference in these closure ti=es is due to the higher venting rate of the scrs= valve pilot air 5.eader during a scra= (operation of solencid valves NC-22 A, 3, C, and D) than that which occurs during operation of the hS6 hand-switch (operation of solenoid valve NC-22E only).

Cn-line surveillance testing is of necessity li=ited to operation of the hS6 handsvitch.

Ite= 3 37 procedures, require that the SDV vent and drain valves be nor= ally Operable, cpen and periedically tested.

If these valves are not operable or are closed for = ore than one (1) hour in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period during operation, the reason shall be logged and the NRC notified within 2k hours (Prc=pt Notification).

Resronse to Ite: 3 3ig Rock Point operating procedures already address scra= du=p tank vent and drain periodic testing and require that the valves be ner= ally open and cperable. A re-vision to these procedures-has been =ade to incorporate Prc=pt Notification (vith-in 2h hcurs) for inoperability of the valves.

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Review instances in which water ha==er or danage which =ay have been caused by water ha==er has occured in SDV related piping.

Identify the cause and corree-tive acticn for each instance.

Response to Ite: 4 No instances were identified during the review of plant - reccrds in which water ba-er or da= age.vhich =ay have been caused by water ha-er have occurred in 30V-related piping.

Ite= 5 Reviev surveillance-procedures to ensure that degradation of any SDV level switch due to a da= aged ficat or other cause would be detected and that inoperability frc=_any cause would be reported to the NRC.

Res;cnse to Ite= 5 Existing _ surveillance precedures address surveillance of the SDV level switches.

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Mr Ja=es G Keppler 3 -

31g Rock Point Plant July 31,.1980 Instances of such degradation are considered reportable in accordance with Technical Specifications, Section 6.9.2.b.(1).

Ite= o If no functional-test or inspection which would detect degradation of each SLV level switch has been performed during the past three (3) =onths, =ake provis-ions to perfor= an inspection and functional test of all SLV level-switch asse=-

blies at the next reactor shutdown of greater than h8 hours duration.

Response to Ite: 6 Functional testing of each scra= du=p tank level switch was last perfor=ed on October 14, 1979 Accordingly, this testing and associated inspection has been scheduled to be perfor=ed during the next reactor shutdown of greater than 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> duration.

31g Rock Point Plant has recently completed scram tests pursuaat to II 3ulletin No 60-17 which demonstrated the satisfactory design and operaticn of the scrs=

discharge volume system. No instances of equipment =alfunction or inadequacy were observed.

The cover letter to II Bulletin No 80-14 requested an esti= ate of the =anpower expended on this Sulletin. Review and response preparation expended approximate-17 h0 =an hours. Corrective actions involved an esti=ated one (1) =an-hour for incorporation of new reporting requirements into existing operating procedures.

David ? Hoff=an (Signed)

David ? Hoff=ss Nuclear Licensing Administrator CC - Director, Office of Nuclear Reactor Regulation Director, Office of. Inspection and Enforcement URC. Resident Inspector - Big Rock Point Plant 1

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