ML20004D410
| ML20004D410 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/01/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 LAC-7573, NUDOCS 8106090362 | |
| Download: ML20004D410 (3) | |
Text
e DlDA/RYLAND
[k COOPERAT/VE Po BOX 817
- 2615 EAST AV SOUTH
- LA CROSSE. WISCONSIN f>1601 (608) 788 4 000 June 1, 1981 In reply, please refer to LAC-7573 DOCKET NO. 50-409 A
Director of Nuclear Reactor Regulation p
ATTN:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 3
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U. S. Nuclear Regulatory Commission "M// g O
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SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
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PROVISIONAL OPERATING LICENSE NO. DPR-45 CONTROL OF HEAVY LOADS i
Reference:
(1)
NRC Letter, Eisenhut to All Licensees of Operating Plants and Applicants for Oper-ating Licenses and Holders of Construction Permits, dated December 22, 1980.
Gentlemen:
Reference (1) requested that we review our controls for the handling of heavy loads to determine the extent to which the guidelines of NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants" are presently satisfied at LACBWR, and identify the changes and modifi-cations that are required in order to fully satisfy the guidelines of NUREG-0612.
The following information is presented in answer to specific re-quests of Reference (1).
Reference (1) specifically requested that the interim actions of be implemented as soon as possible.
contained the staff position on the following interim actions:
(1)
Safe load patha should be defined per the guidelinea of Section S.1.1(1) of NUREG-0612.
LACBWR developed and implemented safe load paths for the movement of heavy loads to circumvent the reactor vessel, and safe shutdown equipment.
The movement of heavy loads over spent fuel in the FESW is inevitable at LACBWR.
The load path, analysis, and USNRC approval, for moving heavy loads into the FESW is addressed in submittals for Amendment No. 4 to License No. DPR-45, and USNRC Safety Evaluation Reports, dated October 22, 1975, and July 13, 1979, revised February 4, 1980. i f 8106090g
l Mr. Dennis M. Crutchfield, Chief LAC-7573 Operating Reactors Branch No. 5 June 1, 1981 (2)
Procedures should be developed and implemented per the guidelines of Section 5.1'1(2) of NUREG-0612.
Procedures have existed in the LACBWR Operating Manual, Volume VI, Sections 2 through 7, since the existence of the plant for handling all of the removable items required for reactor refueling operations.
Volume VI, Section 13, of the Operating Manual refers to handling a spent fuel shipping cask, and in accordance with requirements of this section, detailed procedures have been developed and knplemented for each spent fuel shipment, the earliest occurred in November 1970 and the latest occurred in May 1981.
Detailed procedures for lifting other plant equipment (e.g., Forced Circulation Pumps) have been utilized, avoiding of handling operations over or in proximity to irradiated fuel or safe shutdown equipment.
(3)
Crane operatore should be trained, qualified and conduct thcmceives per the guidelines of 5.2.1(3) of NUREG-0612 All crane operations are conducted by operators trained and qualified per LACBWR Administrative Control Procedure 23.1, which incorporates guidelines of ANSI B30.2-1967, " Overhead and Gantry Cranes".
(4)
Cranes should be inspected, tested and maintained in accordance uith the guidctines of Section 5.1.1(6) of NUREG-0612.
LACBWR utilizes the mechanical maintenance preventive maintenance program to schedule and record crane inspections and tests.
Machinery history records maintenance performed on the cranes.
The crane in-spection program with attendant procedures and records have been in use at LAC.3WR since 1970 and the program is based on the guidelines of ANSI B39.2-1967 and OSHA 1910.179.
The provision that, for cranes having limited usage, the tests should be performed prior to their use is utilized by LACBWR.
However, even on these cranes, inspections and maintenance are performed routinely.
(5)
In addition to the above, special attention should be given to procedures, equipment, and personnet for tha handling of heavy toads over the core, such as vesset internate or veeeet inspection toots.
This speciat reviev should include the following for these toads:
(1) revieu of proceduree for instattation of rigging or lifting devices and movement of the toad to accure that sufficient detait is provided and that instructione are clear and concise; (2) visuat inop'ections of toad,
o e
Mr. Dennis M. Crutchfield, Chief LAC-7573 Operating Reactors Branch No. 5 June 1, 1981 bearing components of cranes, stings, and special tifting devices to identify flaus or deficiencies that could toad to failure of the component; (3) appropriate repair and replacement of defective componente; and (4) verify that the crane operatore have been property trained and are familiar uith specific procedures used in handling these loads, e.g.,
hand signals, conduct of operatione, and content of procedures.
Prior to each refueling, i.e.,
the handling of heavy loads over the core, the procedures are reviewed and revised as necessary, reviewed by the Operations Review Committee and approved by the Plant Super-intendent.
The special handling and lifting equipment is assembled, inspected and functionally tested, if applicable.
Any replacement or repairs are made at this time prior to use in the refueling.
Crane operators qualification is verified and training on the approved procedures is conducted prior to handling core and vessel components.
The above actions by LACBWR fulfill the request for implementation of the interim actions described in Enclosure 2 to Reference (1).
The request for a report documenting the results of a review and the required changes and modifications will be included in a subse-quent reply to Reference (1).
If you have any questions, please contact us.
Very truly yours, DAIRYLAND POWER COOPERATIVE W
b Frank Linder, General Manager FL: HAT:af cc:
J. G. Keppler, Reg. Dir., NRC-DRO III NRC Resident Inspectors
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