ML17252B484

LER 76-063-00 for Dresden, Units 2 and 3 Re Radiation Protection Personnel Reported That Stack Gas Sample Pump Flow Appeared to Be Abnormally Low

ML17252B484
Person / Time
Site:	Dresden
Issue date:	11/01/1976
From:	Stephenson B Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
BBS LTR 76-768 LER 76-063-00
Download: ML17252B484 (3)

Text

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• Dresden Nuclear Power Station* *

"~-:;ri: 111inois 1

60450 Telephone 815/942-2920

'Re~fafoty*l '

BBS Ltr. #76-768 November 1, Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U. S. Nuclear. Regulatory Commission 799 Roosevelt Road

• . Gleri Ellyn, Illinois 60137 REEERENCES: Docket No. 50-237 Docket No. 50-249 Enclosed please find Reportable Occurrence report number 50-237/1976-63.

This report is being submitted to your office in _accordance with the Dresden*

Nuclear Power Station Technical Specifications, Section 6.6.B~

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~B .. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc: Director of Inspection & Enforcement-Dir~ctor of Management Information & Program Control File/$C.

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. 30 I 10131 31 32 REPORT REPORT CATEGORY TYPE. SOURCE . DOCKET NUMBER EVENT DATE REPORT DATE

• @E]coN'T I I I lhJ lbJ 101s101..:..101~13171 .l*t 101013171'1 ll It IOl'/17101 7 8 57 58 59 . 60 61. 68 69 74 75 80 EVENT DESCRIPTION

!ill] I PUR1tJG- NOR.l'Ylr.*L. OPERATION, RADtAT1oAI PRoT£C.TtON 'P£R.SoNNEb- RE.PORTED THA-f I*

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7 8 9 PRIME (SE£ 1!111\GH'ED SJ..1££T) BO.

SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION 7

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LYJ 48 CAUSE DESCRIPTION

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. *' STATUS  % POWER OTHER STATUS ' DISCOVERY DISCOVERY DESCRIPTION EE] 1£J Io Iq 17 I NA I lB_J )Jf't 7 B 9 10 12 13 44 45 46 80 FORM OF ACTIVITY CONTENT Rf1121 r RELEASED 1z 1

• OF RELEASE 1~1

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45 j./ft LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ,~

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_._M_~.;.._-~,~-----------------' 80 OFFSITE CONSEQUENCES

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7 8 9 . 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION ETul .LZJ JtJ11-7 8 9 10 80 PUBLICITY E0.B 9 7 80 ADDITIONAL FACTORS 7

Elfil 8 9 80 7

ITifil8 9' . 80 PHONE: £X.'J. 2_(;,5 GPO 881

• 667

EVENT DESCRIPTION (Continued) states that during plaJ*¢g,µt"i~sts,~,--when both pumps must be out of service, the steam jet air ejector 'mc:lnit-cirs may be used to satisfy the plant chimney monitoring requirements if the reactor is operating at a steady-state power leve!.~) Although a plateout test was not being performed *when both pumps were forced out of service, the reactor had been operating in a steady-state condition for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />, and both steam jet air ejector monitors were operable.

During the period from 1725 to 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />, while the 2/3 "A" sample pump and suction filter were being replaced to provide rapid compliance with Tech Spec requirements, the steady-state operation of the unit .and the static response of the SJAE monitors ensured that no unacceptable releases occurred. Because the cause of failure could not be readily identified on the 2/3 "B" sample puiip ,. it was *decided to first restore the operability of the "A" sample pump by simply replacing the pump and suction filter. This* is not a repetitive occurrence. (50.-237 /1976-63)

• CAUSE DESCRIPTION (Continued) conditio'!} on, the 2/.3 "B" _pump .was :caused by r.:?af1t improper valv~ lineup.

' . ; . ~~*~-:--*' . ~ *...

As stated above, the 2/}3 :"A" sample pump. and suction, filter were replaced.

The 2/3 "B" sample pump wa~ *returned to service a~*112:S hours on ..10-:4-76, after the valving error was discovered. Since this is an isolated event,. regularly scheduled maintenance-should be adequate to prevent recurrence. *