ML17252A465

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Submittal of Licensee Event Report 03L-0, Reactor Protection System or Engineered Safety Feature Instrument Settings
ML17252A465
Person / Time
Site: Dresden  
(DPR-019, DPR-025)
Issue date: 07/10/1978
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
Download: ML17252A465 (2)


Text

Comm..

  • ealth Edison Dresden ear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #78-1047 J\\Uy 10, 1978 James G. Keppler;, Regional I;lirector Directorate of Regulatory Operations.- Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road G.len Ellyn, IL 60137 *

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Reportable Occurrence Report #78-027/031-0, Docket #OSO~is hereby

. submitted. to. your office in accordance with Dresden Nuclear Power.Station Technical Specification 6.6.B.2.(a), reactor protection system or.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 fulfill~ent of the functional requirements of affected systems.

BBS/kmh Enclosu:r.e nson Station Sup~rintendent Dresden Nuclear Power Station CC:

Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC JUL 1 81978.

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,. NRC mum

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"ff.111d't.'t'l!fm'lft'G'ot.'""°""'t'OMM1'S$'1("1 17-77)

LICENSEE EVENT REPORT**

..,Y -::~~cl~TROL BLOCK: I *.1. 1 * *

  • 10.
  • (PLEASE PAI.NT olvPE ALL REQUIRED INFORMATION)

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IIILIDIR!sl3IG)lo lo I-lo lo lo lo lo 1-- lo lo 1014111111! 1101 I IG) 7 B

9 LICENSEE CODE 14 15 LICENSE NUMBE~.

. 25 26 LICENSE TYPE JO

  • 57 CAT 58 CON'T

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~;~~~~ W©l o I 5 I o I o I o I 2 I 4 I 9 101 o I 6 12 11 I 7 I a '(V lo ! 711 Io I 7 I a I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE i4 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@*

I While performing sur'1. DIS 250-1, MSL Hi Flow !sol. Sw. dpis* 3-261-2C tripped at

@JI] I> 130 psid *.

(T.S. limit</=115.9 psid 120% Flow; Table 3~2.1). The.16 MSL Hi Flow

[TITI I !sol switches l)rovide containment isolation protection whenev:er primary integrity.regu!red.

[)))) 1safety significance minimal because both trip sys~.were operable and would have

[))))*!isolated containment at 111.Spsid,.conservative to T.S. limit of 115.9psid. *Similar1

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I events ref. in LER/1050-249/1977-4 & 78-022/03L-0.

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7 B 9 BO SYSTEM CAUSE CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE

.* SUBCODE I I IB~I@ l§J@ 'LLJ@-1 I IN Is IT IR I u-1@ L!..J* tu@*;:-~ ~...

9 10 11 12 13 18 19 20 I:":;\\

LE R/RO CV ENT YEAR

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REPORT I 7 I 8 I NUMBER 21 22

  • .SEQUENTIAL OCCURRENCE*

REPORT REPORT NO.

CODE TYPE I I I o I 21 Tl 1.......-1 Io I 3 I lLl l=J 23 24 26 27 28 29 JO 31 ACTION FUTURE EFFECT SHUTDOWN

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ATTACHMENT NPRD-4 PRIME COMP.

TAKEN ACTION ON PLANT METHOD

.. HOURS ~ SUBMITTED FORM :;us.

. SUPPLIER l!.J@l!.J@ L!J@

~ I o Io I o Io 1.. L!J@

L!J@ Li@

33 34 35 36 37 40 41

. 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@

REVISION NO.

l.QJ 32 COMPONENT MANUFACTURER I BI 0 I 8 I 0 I@

44 47

!III] I Cause attributable to. apparent corrosion deposits in meter movement gear teeth.

Gears I ITIIl twere cleaned and switch was promptly reset to Dr.'esden setpoint. of 113+/-2. psifi

  • I o::::ITJ jincreasing.

Other switches checked satisfactorily.* The (16) MSL Hi Flow !sol. Sw's

[J))] jwill continue to be tested monthly using DIS 250~1.

No* further corrective action

~

tdeemed necessary.

7 B

9.

FACILITY STATUS

% POWER rJ:ITl l.§J@ I o I 9 I 4 l@.._I --"'N"""'A......_ __

. OTHER STATUS @

80 METHOD OF

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DISCOVERY DISCOV.ERY DESCRIPTION L!!J~~'----S~u~rv:..;..;e~i~l~l~an==c~e:....:.T~e~s~ti~n~g:.-____________ -'I 1

  • 0 9

10 12 n

44 ACTIVITY CONTENT.

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. RELEASED OF RELEASE AMOUNT OF.ACTIVITY ~

ITEl w@ LI..l@I NA I

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9 10 11 44.

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. LOCATION O~ RELEASE @.

NA 80 PERSONNEL t:XPOSURES

  • (.:;:;\\

NUMBER

(.;':;\\TYPE

. DESCRIPTION ITI2J I o I o I o l0L!J@..__, ____ __..._...... N._A...__ ________________ __.

1 8

9 11 12 13 PEFISONNEL INJURIES

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NUMBER DESCRIPTION~

ITE] Io Io Io l@'-----------.......... ------------..,....------

1 8

9 11

  • 12 BO LOSS OF OR DAMAGE TO FACILITY."4J'I.

TYPE DESCRIPTION o,;:::,J

[QI) !.Aj@)~-..,....--*-,_-------N=A..__ _______________ ___.

8 9

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.80 80 PUBLICITY

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  • ISSUEDt,;:;\\ D. ESCRIPTION ~

NRC USE ON l y j

  • ITTIJ 11Ll6~** ----* __________

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I I I I I I I I r I., I I r.

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10 68 69 *

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NAMEOFPREPARER*----:C~a~r~l**-I~.*

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