ML20117E079
| ML20117E079 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/13/1996 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-002, IEB-96-2, W3F1-96-0074, W3F1-96-74, NUDOCS 9605150389 | |
| Download: ML20117E079 (3) | |
Text
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l Ente gy Oper'tions,Inc.
Killona, LA 70066 Tel 504 739 6242 James J. Fisicaro
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W3F1-96-0074 A4.05 PR May 13,1996 U.S. Nuclear Regulatory Commission l
ATTN: Document Control Desk l
Washington, D.C. 20555 i
Subject:
Waterford 3 SES l
Docket No. 50-382 License No. NPF-38 NRC Bulletin 96-02," Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or Over Safety-Related Equipment" Gentlemen:
l This submittal is in response to NRC Bulletin 96-02, dated April 11,1996. The i
subject bulletin was written to alert operating nuclear plant Licensees to the l
importance of complying with existing regulatory guidelines associated with the control and handling of heavy loads at nuclear power plants while the plants are operating (in all modes other than cold shutdown, refueling, and defueled). The l.
bulletin was written to remind licensees of the responsibilities for ensuring that heavy load activitics carried out under the license are performed safely and within the requirements specified under Title 10 of the Code of Federal Regulations.
Backaround:
NRC letter dated December 22,1980 transmitted a copy of NUREG-0612 and l
requested that we evaluate the control of heavy loads utilizing overhead cranes.
l Waterford 3 responded to the interim actions requested by the NRC via W3P81-l 1188 dated May 15,1981. Waterford 3 transmitted (via letter W3P81-1513, dated i
6/19/81) Part I of a report which covered the general requirements for overhead handling systems at Waterford. Part ll of the report was transmitted via letter W3P81-2158 dated 9/28/81, which covered specific requirements for overhead handling systems operating in the vicinity of the spent fuel storage pool, in the 9605150389 96oS13' PDR ADOCK 0500o302 fik )
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1 NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or Over Safety-Related Equipment"-
W3F1-96-0074 Page 2 May 13,1996 containment, and in plant areas containing equipment required for reactor shutdown, core decay heat removal, or spent fuel cooling. The NRC posed questions, requiring 1
LP&L to perform an analysis of the effects of dropping any load handled by the containment polar crane. In a series of correspondence and actions that followed, Waterford 3 proceeded to address and resolve NRC Staff questions and comments associated with the Waterford 3 program for handling of heavy loads.
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In SSER 6, Section 9.1.4 (Fuel Handling System) dated June 1984, it was stated that the NRC staff and its consultant, Idaho National Engineering Laboratory (INEL), had reviewed the Waterford 3 submittal describing provisions for the handling and l
control of heavy loads at the Plant. It was further stated that as a result of this-l review, INEL had issued the technical evaluation report (TER) shown in Appendix l l
of SSER Supplement 6. _ The Staff concluded that Phase I of NUREG-0612 for Waterford 3 was acceptable. A condition was included in the Waterford 3 operating license pending the Staff review of Phase 11 of NUREG-0612 for Waterford 3.
In SSER 8, Section 9.1.4 (Fuel Handling System) it was stated that the staff no longer considered the license condition (identified in Supplement 6 of the SER) necessary on the basis of improvements in the handling of heavy loads obtained by implementation of NUREG-0612, Phase I, and the results of Phase ll reviews at other plants. The Phase ll license condition was removed from the Waterford 3 operating license on the basis of generic resolution.
In a May 6,1986 letter the NRC further concluded that, consistent with NUREG-0612 and Generic Letter 85-11, the issue of heavy loads handling was complete at Waterford 3.
Response
As requested in the subject bulletin (96-02), Waterford 3 has reviewed plans and capabilities for handling heavy loads (e.g., spent fuel dry storage casks, reactor cavity biological shield blocks) in accordance with NUREG-0612 (Phase 1) and Generic Letter 85-11 and within our licensing basis as previously analyzed in the FSAR. Waterford 3 continues to maintain an adequate, active program for handling heavy loads, including procedures for operating, maintaining, and testing the cranes involved. The Waterford 3 program covers the Reactor Containment Building Polar Crane, the Fuel Handling Building Bridge Crane, main and auxiliary hoists, and the
t NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the 1
Reactor Core, or Over Safety-Related Equipment" W3F1-96-0074 Page 3 l
May 13,1996 i
i Reactor Containment Building Auxiliary (Pedestal) Crane. Per procedure, only i
i trained and certified personnel are permitted to operate these cranes. Waterford 3's procedure for handling heavy loads (UNT-007-008) adequately prepares the plant
- for future handling of applicable heavy loads. The procedure provides administrative controls that are consistent with the intent of NUREG-0612.
Waterford 3 currently has no established plans to (over the next two year period)
. move any applicable heavy loads (greater than 1500 pounds) over safety-related equipment while the plant is operating at power. Hatch Covers, that qualify as heavy l
loads, will be moved in the Fuel Handling building (while at power) during the receipt of new fuel- (Prior to Refuel 8) and to allow bringing in refuel / outage equipment.
j-However the hatch covers are not transported over the Spent Fuel Pool area nor j
over other safety-related equipment during this activity. Interlocks prevent the crane j
from traveling into that area. The covers are listed under the procedure for handling heavy loads. Waterford 3 currently has no spent fuel dry storage casks on site and
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has no immediate plans to obtain any. There are no reactor cavity biological shields in the Containment Building to be lifted by a crane. The missile shield,' over the j
Reactor Vessel area is of a roll-away design and does not require being lifted by a crane.
However, Waterford 3 is currently evaluating spent fuel capacity on site. If the decision is made to increase spent fuel storage capacity by way of dry cask storage, j
there would not be any associated heavy load handling over spent fuel, On the j-other hand,~ if the decision is made to re-rack the existing spent fuel pool, there
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would be the possibility of involving heavy load handling over the spent fuel pool. In the latter case, fer any heavy load handling outside of the licensing basis, Waterford 3 would comply with NRC Bulletin 96-02 and submit an appropriate license amendment request (6-9 months) in advance of movement of the load.
NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the l
Reactor Core, or Over Safety-Related Equipment" W3F1-96-0074 Page 4 i
l May 13,1996 l
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Should you have any questions concerning this response, please contact me at (504) 739-6242 or Don Vinci at (504) 739-6370.
l Very truly yours, d
h l
J.J. Fisicaro Director Nuclear Safety JJF/ OPP /ssf cc:
L.J. Callan, NRC Region IV C.P. Patel, NRC-NRR R.B. McGehee N.S. Reynolds NRC Resident inspectors Office l
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