05000237/LER-1979-001, Forwards LER 79-001/03X-1

Forwards LER 79-001/03X-1

ML17173A817
Person / Time
Site:	Dresden
Issue date:	05/03/1979
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A820	List: 05000237/LER-1979-001, Forwards LER 79-001/03X-1
References
79-317, NUDOCS 7905220257
Download: ML17173A817 (2)

LER-1979-001, Forwards LER 79-001/03X-1

Event date:
Report date:
2371979001R00 - NRC Website

text

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May 3, 1979 BBS LTR f/79-317 James G. Keppler, Regional Director Directoratec::of Regul~tory Operations -.Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Revised Reportable Occurrence Report f/79-l/03X-l, Docket 11050-237 is hereby subin:Utted to your office in accordance with Dresden Nuclear Power Stat:i:6n Technical Specification 6.6.B.2.(b), conditions leading to operation/in *a degraded mode permitted by a limiting condit:i:6n:.>.for operation.

C.?.u*~e codes 12 and 13 have b.een revised to. reflect an operator error as the**-principal cause of this event.

Station Dresden Power Station BBS/leg Enclosure cc:

Director Inspection & Enforcement Direc~or of Management Information & Program Control File/NRC Aoo':l \\ S t I I

i (7-77) i

- ICENSEE EVENT REPORT UPDATE REPORT l

PREVIOUS REPORT: 1/31/79 CONTROL"'8LOCK: I

• 1*10 (PLEASE PRINT OR TYPE AL

.EOUIRED INFORMATION) i 1

6

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I I I LI DJ' R *f~& 1 2 JG)I 0 I 0 1-I 0 I 0 I 0 I 0 I 0 1-I 0 I 0 101 4 I l I l I l I 1101 I. 10 j_-_:!..__8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25.. 26

. LICENSE TYPE :lO 57 C~T 5B

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• 1 7 101 o 11 I o 13 I 7 19. 101 o I s I o I 31 7 I -9. I G).

7 8 --* 60 -----

. 61 _

DOCKET NUMBER 68 69

• EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND ~~-OBABLE CONSEQUENCES@

[]JI] I During steady state operation the torus level increased to -1 inch, due to re-l petitive starts of the HPCI turbine *.

• See R0/179-Z/OlT-0. '.Immediate operator action I_

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was to pump the excess torus water to the 'hotwell, restoring. water level t.o -3.5" L'((ill LI ___________________________________

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which is within specifications *. This event had*minimal safety significance since the 0. 5 inch excess in water level did not* significantly affect 'the pressure sup-I

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T.s: req's level maintained between '.-1.5 and -4.75" at lff P/P.

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.- IJ.E I Increase in the torus water level was determined to result from operator oversight.

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-~-.r I ITTIJ surveillance *will -.be ~changed. to *:inc1ude* a °CAUTION11* statemen.t so: the t"orus' level :will : I -~:2

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no:t* exceed specificatio_ ns during repetitive starts of the HPCI. turbine *. No further 1*

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