ML20084S503

RO 50-254/76-29:on 760809,surveillance of Primary Containment Oxygen Concentration Revealed Increase in Concentration from 4.2 to 4.8%.Caused by Instrument Drift. Oxygen Analyzer Recalibr

ML20084S503
Person / Time
Site:	Quad Cities
Issue date:	09/09/1976
From:	Kalivianakis N, Meis E COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NJK-76-338, RO-254-76-29, NUDOCS 8306170071
Download: ML20084S503 (399)

Text

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Co writh Edison Quad-Cities Nuclear Power Station

• - Post Office Box 216 ~/ _.j Cordova, Illinois 61242 Telepnone 309/654-2241 3 g.._ cgpy., ,

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September 9, 1976 J. Keppler, Regional Director Office of Inspection and Enforcement Region 111 -

U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

Reference:

quad-Cities Nuclear Power Station Docket No. 50-254, DPR-29, Unit 1 Appendix A, Sections 3.7.A.S.a, 6.6.B.2.b Enclosed please find Reportable Occurrence Report No. R0-50-254/76-29 for Quad-Cities Nuclear Power Station.

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This report is submitted to you in accordance with the requirements of Technical Specification 6.6.B.2.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 8

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N. J. Ka1ivianakis WPY SENT REG 10'

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Station Superintendent NJK/ ELM /ik cc: G. A. Abrell l SEp 101976 ,

1 l 8306170071 760909 DR ADOCK 05000254 PDR

LJ LICENSEE EVENT R RT A ' -

CONTROL BLOCK:l l l l l l l (PLEASE PRINT ALL REGulRED INFORMATION) 1 6 N E LCENSE NUMBER YPE TYPE o1 ll l L l Ql Al Dl1 l 7 89 14 l0 l0 l-l 0l 0l0 l0 l0 l-l0 l 0 l 15 25 l4l1l1l1l1l 26 30 l0l3l 31 32 CATEGORY TY P 00CKET NUMBER EVENT DATE REPORT DATE O

7 8 CON'T l 57 l

58 l W59 lL l 60 l0 l 5 l 0 l-l 0 l 2 l 5 l 4J S1 68 l 01 8l 0l 91716 l 69 74 l0 l9 lo 19 l 7 l 6 l 75 80 EVENT DESCRIPTION HE l Normal operator surveillance of the primary containment 02 concentration as Indicated l 7 89 -

80 Eg l on the main control room panel 912-7 revealed an increase in 02 concentration from l 7 89 80 EE l 4.2% to 4.8% in a period of 12 hrs. A sample was taken at 8:45PM on 8-9-76 from the l 7 89 80 EE l drywell and the 02' content found to be 5.7% which is in excess of the 5.0% limit l 7 89 eO HE l given in Technical Specification 3.7.A.S.a. Immediately after the test results were l l 7 89 pnug 80 DE CODE COMPONENT CODE SUPPUER R V0tATION EE l SlE l W 7 89 10 11 l 1 l N l Sl Tl Rl VJ 12 17 W 43 44 lBl1l3l5l 47

[NJ 48 CAUSE DESCRIPTION gg l (Proximate Cause-Equipment Failure) instrument drif t was experienced on a Beckman l 7 89 80 El l Instruments Inc. Oxygen Analyzer model 1250. Corrective action.has been deemed l 7 89 80 DE l adequate to prevent further occurrences of this type. l STA  % POWER OTHER STATUS OtSCOVERY 06COVERY DESCRIPTON 1

7 8 9 lE l l0l8l0l l 10 12 13 NA l 44 W45 4ts l NA J

80 RE EAS O OF L SE AMOUNT OF ACTMTV LOCATOff CF RELJASE E0 7 8 9 W dl10 11 NA l 44 l

45 NA l 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTON DE l 0l 0l 0 l yl NA l 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTON 3[ l 0l0 l 0 l l NA l

7 89 11 12 80 OFFSITE CONSEQUENCES DG l NA l

7 89 80 LOSS OR DAMAGE TO FACIUTY TYPE DESCRPTON B2 [ Zj l NA l 7 89 10 80 PUBUCITY BE l Nk l 7 89 80 ADDITIONAL FACTORS D[ l (Event Descrp. cont.) known a load decrease was ordered at the rate of 3 MWe/hr in l 7 89 80 DE I anticipation of possibly having to shutdown the reactor in compliance with Technical l 7 89 80 NAME: Eric L. HeI1s

• PHONE:

GPO 809 687

V ADDITION'AL FACTO S (Event Description cont)

Specification 3.7.A.5.b. Additionally,the Instrument Maintenance Department was requested to check the calibration of the oxygen analyzer. Makeup N2 was added to the drywell and the drywell atmosphere was Intermittently purged to reduce the 02 content. At 11:15 p.m. containment 02 concentration as determined by sample analysis was below the 5.0% Technical Specification limit. On 8-10-76 the oxygen analyzer was recalibrated and satisfactory operation was obtained. Instrument drift has been experienced twice before on the Unit Two oxygen analyzer. (R0 50-254/76-29).

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