ML20106E368

Provides Minor Changes to List of Testing Deficiencies to Be Completed After Fuel Load.Original List Provided in LO Delgeorge to HR Denton.Deficiency Resolution Can Be Deferred for Period Proposed in

ML20106E368
Person / Time
Site:	Byron
Issue date:	10/19/1984
From:	Tramm T COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
9354N, NUDOCS 8410290190
Download: ML20106E368 (2)

Text

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'f '^'T/ OneCommonwealth Edison First National Plaza, Chicago, Ilhnois EJ. 7 Addr:ss Reply to: Post Offics Box 767 -

( ,/ Chicago, lilinois 60690 October 19, 1984 i Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation ,

U.S. Nuclear Regulatory Commission '

Washington, DC 20555 Sub ject: Byron Generating Station Unit 1 Completion of Preoperational Test Program NRC Docket No. 50-454 References (a): September 28, 1984 letter from L. O.

DelGeorge to H. R. Denton.

(b): October 27, 1983 letter from T. R. Tramm to H. R. Denton.

Dear Mr. Denton:

This letter provides minor changes to the list of testing deficiencies to be completed after the Byron 1 fuel load. The original list was provided in reference (a).

Attachment A to this letter supplements and revises the list of testing deficiencies to be completed after fuel load. Several safety injection check valves have been added to the list for SI test 73.13 because Region III I&E inspectors have determined that these valves should have been tested at a higher backpressure to satisfy Technical Specification requirements. The VC 85.10 control room ventilation deficiency has been rewritten because the post-test review of the differential pressure data disclosed that the instrumentation accuracy was sufficient to confirm positive pressurization, but insufficient to confirm the 1/8" differential.

The resolution of these additional and revised test deficiencies can be safely deferred for the limited period proposed for the reasons described in reference (a).

Please address further questions regarding this matter to this office.

Very truly yours,

% r2.1 e-T. R. Tramm Nuclear Licensing Administrator 1m 8410290190 841019 i PDR ADOCK 05000454 \

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ATTACISENT- B ,.

9 TESTING DEFICIEtCIES TO tf OLDfLETED AFTER FUEL LOAD Tech Spec Test Description  % DIicability Completion ih0Jired Prior To SI 73.13 ISI8900A leakacy! f I gpm not demonstrated Mode 2. Initial Criticality (Mooe 2) at 2235 psig RCS pressure.

15189008 leakage $ 1 gpm not demonstrated Moae 2 Initial Criticality (Moae 2) at 2235 psig RCS pressure.

ISI8919A leakage f I gpm not demonstrated Mode 2 Initial Criticality (Mooe 2).

at 2235 psig RCS pressure.

1518919B leakage f 1 gpm not demonstrated Mode 2 Initial Criticality (Moae 2) at 2235 psig RCS pressure.

ISI8919C leakage $ 1 gpm not demonstrated Mooe 2 Initial Criticality (Moce 2) at 2235 psig RCS pIessure.

15I89190 leakage $ 1 gpm not demonstrated Mode 2 Initial Criticality (Moae 2) at 2235 psig RCS pIessure.

IS18956C leakage $ 1 gpm not oemonstrated Moce 2 Initial Criticality (Moae 2) at 2235 psig RCS pIessura.

15189560 leakage $ 1 gpm not cemonstrated Mode 2 Initial Criticality (Mode 2) at 2235 psig RCS pressure.

STATUS: Components tested at less than 1700 BASIS: Leakage pgpm oemonstrated psig. Retest requires operating plant at(1700 psig. Valves shall be conditions. aemonstrated LPEHAULE prior to entering Mode 2 per requirements of Tech Spec Section 4.4.6.2.2. Tech Spec Section 4.4.6.2.2.

VC 85.10 CDntrol room boundary differential pressure Mode 6 For Train A, a positive differential Control Room of 1/8 in. W.C. not acilieved. pressure with respect to ambient will ventilation De completed prior to initial criti-STATUS: A positive differe:1thl pressure with cality (Mode 2). For Train A and B, respect to ambient has been establisted during 1/8 inch w.g. differential with operation of redundant Train B. Train A respect to surrounding areas w111 be balancing damper adjustments in process. A obtained prior to accumulating 10 1/8 inch w.g. differential relative to auxiliary effective full poner days at power building surrounding areas requires the levels not exceeding 251 power, auxiliary building ventilation system (VA).

See reference (D). HASIS: Fission proauct inventory is trivial in comparison to tne inventories employed Dy FSAR barety Analysis, and therefore, will not threaten Control Room habitability.

See reference (b).

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