ML18348A195

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License Event Report 1978-006-00 Re Shipping Cask Movement
ML18348A195
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/02/1978
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/RGN-III
References
LER 1978-006-00
Download: ML18348A195 (2)


Text

  • consumers
  • eOci~f-' 1.-t- Q. CJ P-f Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
  • Area Code 517 788-0550 March 2, 1978 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - ER-78-006 -

SHIPPING CASK MOVEMENT The reverse side describes a reportable occurrence under Technical Specification 3.21 for the Palisades Plant.

David P Hoffman Assistant Nuclear Licensing Administrator CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement

NRC FORM 366

  • Palisades U.S. NUCLEAR REGULATORY COMMISSION (7*77)

LICENSEE EVENT REPORT CONTROL BLOCK: I 1 G) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 C£:E] I Ml I I p I A I L 11 101 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 I 0 101 4 1111 11 11 101 . I I© 7 8 9 LICENSEE CODE 14 ,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T ITIII ~~~~~ W©I o I 51 o Io Io 12 I 5 I 5 101 o I 2111 41 7 I 81@1 o I 3 Io I 2 I 1 I 8 10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

[]JI] I During movement of the incore shipping cask into and out of the contain-

[ill] ment building on 12 and 14 February, respectively, the edge of the cask

!TITI was permitted to pass to the east of the cast boundarz of the tilt Eits.

[IT[] This is contrary to the requirements of TS 3.21.lb. The cask did not

[)))) travel over the spent fuel EOOl. At the time of occurrence 2 the cask

[ill] I was held by a dual lifting sling and was being lifted by the fuel handlin~

[)))) I building crane 100-ton hook. Event had no adverse effect on public / I 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE safety. 80 CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

[ITTI 7 B 1z1z1@

9 10 L.!J@ W@

11 12 1z1z1z1z1z1z1@

13 18

~@ ~@

19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

(;::;'\ LEA/AO CVENT YEAR REPORT NO. CODE TYPE NO.

\!..!.) REPORT NUMBER I7 I 8 I I I 1010161 ~ 10111 W l=J L2J 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 ~ SUBMITTED FORM SUB, SUPPLIER MANUFACTURER W@l.JLJ@ W@ ~ 101010101 W@ W W@ Iz 19 1919 I@

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I Personnel in charge of the movement were not adequately instructed in order to make them aware 9f the requirements of TS 3.21. A procedure which encomEasses the requirements of TS 3.21 was issued prior to ITIIl I subsequent movements of the incore shipp'ing cask into the containment 7

o:m 8 9 buildin .

80 METHOD OF FACILITY STATUS  % POWER OTHER STATUS @ DISCOVERY DISCOVERY DESCRIPTION @

ITTIJ LlLI@ I o I o I o l@I.....-"N......1-...A_ _ ___ UJ@I 8 9 10 12 13 44 45 46 Audit 80 ACTIVITY CONTENT Q.,

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @

[ill] W@ L1..i@)I N/A I N/A 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER (.;:;\TYPE DESCRIPTION

~ I 0 I 0 I 0 1'5'Uj@....._=N'-"A.;__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.

7 8 9 11 12 13 80 PERSONNEL INJURIES ~

NUMBER DESCRIPTION:

~I 010101@)1....._____ ___________________________________________,

l!!_~A 8 9 11 12 80 LOSS o* OR DAMAGE TO FACILITY t4:i'1 TYPE DESCRIPTION \::.:;J

~ ~@).....__~N""""-"A.;_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

8 9 10 . 80 PUBLICITY ~ NRC USE ONLY ISSUEDt,:;:;\ DESCRIPTION :IS I2I£J 8 L!J~_l 9 10

___N~....!::...---------------------68 I I I I I I I I I I I I80I 69