ML19350E783
| ML19350E783 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/19/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 TAC-07727, TAC-08074, TAC-7727, TAC-8074, NUDOCS 8106230516 | |
| Download: ML19350E783 (3) | |
Text
Wisconsin Electnc m coune 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 June 19, 1981 S
s Mr. H.
R. Denton, Director O
Office of Nuclear RE: actor Regulation i
63
-U.
S. NUCLEAR REGULATORY COMMISSION A
L Washington, D. C.
20555 6
QFI Attention:
Mr.
D. Eisenhuc, Director Division of Licensing 9
Gentlemen:
DOCKETS 50-266 AND 50-301 NUREG-0612 - CONTROL OF HEAVY LOADS STATUS OF INITIAL ACTION POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Your letters dated December 22, 1980 and February 3, 1981 requested implementation of the interim actions specified in Enclosure 2 to the December 22 letter by May 15, 1981.
To this end, the following actions have been taken:
1)
Interim safe load paths have been defined and marked on equipment layout drawings.
These paths were defined by inspection rather than by detailed analysis.
A detailed analysis of heavy load handling facilities will be submitted by December 31, 1981.
The interim safe load path drawings are on file at Point Beach Nuclear Plant.
Interim safe load paths have not been physically marked on plant floors because we believe such markings may confuse rather than aid the crane operator.
2)
Plant administrative controls for the use of lifting devices have been revised to reference the interim safe load path drawings.
Existing plant lifting procedures will continue to be observed in lifting heavy loads.
New lifting procedures will be written if they are shown to be required by the detailed analysis.
3)
Crane operators are trained to the existing Point Beach Nuclear Plant operator training program, TRNG 2.1, Revision 0.
This program meets requirements of ANSI B30.2, Chapter 2-3, with the following exceptions with respect to training and operations:
Y f6I f 6196230 %. i h
Mr.
H.'R.
Denton June 19,-1981 1) 2-3.1.7e The warning bell will be actuated only as required to advise personnel of crane movement, rather than continuously during crane motion.
2) 2-3.1.7g The main line disconnect switch will not be left open.
Present operating practice is to leave it shut on some cranes, whether or not they are in use, thus reducing the delay when placing the crane in service.
3) 2-3.1.7n -The cranes will not be de-energized for normal maintenance since some maintenance requires that the power be on.
4) 2-3.1.7o Crane controls will not be tested at the beginning of.each shift.
They will be tested at the beginning of each lifting operation.
5)
Existing Wisconsin Electric medical examinations assure compliance with physical requirements as specified in Section 2-3.1.2b, 3 through 6.
Future medical examinations, to be scheduled as soon as practicable, will include eye examinations to meet the requirements of Sections 2-3.1.2.b.1 and 2-3.1.2.b.2.
4)
Present Point Beach Nuclear Plant maintenance proceduren will continue to be observed.
These maintenance procedures meet the requirements of Chapter 2-2, ANSI B30.2, 1976, with the following exceptions:
1) 2-2.1.2 Inspections required in this section will be performed at the frequency required by current plant maintenance procedures which conform to the frequency requirements of ANSI B30.2, 1976, Section 2-2.1.1.6.2.
2)' The containment polar cranes will be subjected to an OSHA inspection prior to use during the refueling operation.
The major annual inspection will be performed during the refueling operation as time permits.
f
,h Mr. H. R. Denton-June 19, 1981 We will be unable to complete'the six-month report on the schedule which you have requested; we expect to be able to submit the report in September 1981.
It should be noted that this schedule' depends on the work load being imposed on our staff and consultants in conjunction with other NRC bulletins, TMI backfitting, and fire protection modifications.
If there are any questions regarding this information, please contact us.
Very truly yours, C'
6" w
C. W. Fay,' Director Nuclear Power Department Copy to NRC Resident Inspector
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