ML17252B508

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LER 77-043/03L-0 for Dresden, Unit 2 Re Drywell Hi Pressure Switch PS2-1501-62A Tripped at 42.9 H20 Increasing Pressure
ML17252B508
Person / Time
Site: Dresden Constellation icon.png
Issue date: 10/28/1977
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS LTR #981-77 LER 77-043/03L-0
Download: ML17252B508 (2)


Text

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  • -, Commonwe*Edison e . Dresden Nuclea;'Wwer Station RR. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR /1981-77 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report /177-043/03L-0, Docket /1050-0237 is hereby submitted to your office in accorda~ce with Dresden Nuclear Power Sta-tion Technical Specification 6.6.B.2.a., engineered safety feature instrument settings which are found to be less.conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

Dresden Enclosure cc: Director of Inspection &'Enforcement Director of Management Information & Program Control File/NRC ocr 31 1s11

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I I . I Ir,'\ . (PLEASE PRINT OR TY.PE ALL REQUIRED INFORMATION)

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1 *. 8 60 61 DOCKET NUMBER 68 .69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ~ND PROBABLE CONSEQUENCES@ . * . .. _ .

[:0--t 2-t*tD.ur:i-ng monthly surveillance DIS 1500-3 Drywell Hi Pressure Switch PS2-1501-62A tripped I

. [QTIJ I at 42.9" H20 increasing pressure. The Tech; Spec. Limit is J -t/-.rs~PSIG.~J(~-:9<7-=ff<7~.:_;,f

41. 6" H20) tables 3.. 2. 2. & 4. 2 .1. The unit is being refueled. The safety implications

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were minimal because remaining three redundant switches were operable and would have I provided@ containment spray permissive within Tech Spec Limits. This is the first

[£12]. occurrence of ~nstrument :4_;rift. on.-,th¢~~-tcllgs

((ill 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUB CODE SUBCODE

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11 12. 13 rl NI sl Tl RI ul@ UJ@ LlJ@

18 19 20 SEQUENTIAL OCCUR REN CE REPORT REVISION LEA/RO LVENT YEAR REPORT NO. _ CODE TYPE NO.

@ REPORT NUMBER I I I7 7 I I I 01 41 3J I /I IoI 3 I ~ l=J ~

21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN . r:::::;.. ATTACHMENT NPRD-4 PRIME C.OMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS \!31 SUBMITTED FORM $UB. SUPPL! ER MANUFACTURER W@l2.J@ W@

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37 01 01 01 01 40 L.!U@

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43 I B I 01 61 91@

44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I The cause is attributed to instrument drift . . The switch was readjusted to 3S.8" H20.

[III] I PS~2-1501-62A is a \I;\arksdale Model D2 X 18 - UL. No further corrective action is deemed necessary at this time. I ITEl 7 B 9 80 FACILITY '3i)\ METHOD OF (.;:;\

STATUS  % POWER OTHER STATUS ~ DISCOVERY DISCOVERY DESCRIPTION

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7 8 9 10 12 11 44 45 46 80.

ACTIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE

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.7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER (::;'::;\TYPE DESCRIPTION

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7 8 g. 11 12 13 80 PERSONNEL INJURIES Q NUMBER DESCRIPTION~

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11 ~12------------------------~--------------8~0 NA LOSS OF OR DAMAGE TO FACILITY Q TYPE DESCRIPTION v::.::J Eli1 W@ * ... NA 7 B 9 10 . so PUBLICITY ~ R SE 1swEDQ DESCRIPTION~ N c u ON Ly "'

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7 8 9. 10 68 69 80 ;;

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