ML20149M330
| ML20149M330 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/10/1996 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | Jeffery Wood CENTERIOR ENERGY, TOLEDO EDISON CO. |
| References | |
| IEB-96-002, IEB-96-2, TAC-M95579, NUDOCS 9612160182 | |
| Download: ML20149M330 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
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December 10, 1996 Mr. John K. Wood Vice President - Nuclear, Davis-Besse Centerior Service Company c/o Toledo Edison Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO BULLETIN 96-02,
" MOVEMENT OF HEAVY LOADS OVER SPENT FUEL, 0VER FUEL IN THE REACTOR i
CORE, OR OVER SAFETY-RELATED EQUIPMENT" - DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 (TAC NO. M95579)
Dear Mr. Wood:
The NRC staff has evaluated the responses to Bulletin 96-02, " Movement of Heavy Loads over Spent Fuel, over Fuel in the Reactor Core, or over Safety-Related Equipment," and found that some licensees without single-failure-proof cranes have analyzed or are planning to analyze postulated spent fuel storage cask and transportation cask drop accidents to establish design basis accidents for their facilities.
Typical cask drop analyses for in-plant cask movement have addressed the effects of a drop on plant equipment and/or cask integrity. Those analyses have assumed that the cask was in its final condition with its structural lids bolted or welded in place and that the fuel remained in the cask at all times, though the integrity of the cask might be breached during the cask drop.
However, since most cask lids are not secured until after the casks are removed from the pool, it is conceivable that a cask could drop in a tipped-over orientation. The cask could also be dropped back into the spent fuel pool or adjacent area, possibly dislodging the cask lid or dislodging the cask lid and ejecting some or all the spent fuel elements onto the top of the spent fuel racks, the floor of the pool, or adjacent areas.
This accident scenario involves the potential for dropping the cask during movement from the spent fuel pool to the area within the plant building where activities such as drying, inerting, and final securing of the cask lid are completed. Off site dose effects are not expected from a cask drop and tip-over event in which there is a loss of both the cask lid and fuel confinement.
However, the effect of such an event on the operation of the facility needs to be assessed.
For example, evaluations may need to be completed to determine if any vital plant areas are rendered inaccessible and if operations or maintenance activities would be significantly hampered. Such evaluations would involve, but are not limited to, the cask and crane designs, the load paths, and the extent to which the licensee can demonstrate its capabil.ity of performing actions necessary for safe shutdown after potential plant damage with resulting radiological sources.
9612160182 961210 PDR ADOCK 05000346 G
1 J. Wood i j
To support further NRC staff evaluation of this potential cask drop scenario while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled), please provide the following:
1.
An evaluation of your crane design, load path, and cask loading and unloading processes that supports a determination that the scenario described above is not credible at your facility, or 2.
If you determine that the event is credible, please provide the following:
(a)
An analysis of a possible drop of a spent fuel storage or transportation cask that results in the tipping over of the spent fuel cask, loss of the cask lid, or loss of the cask lid and ejection of.the spent fuel from the cask into the spent fuel pool or areas adjacent to the pool. This load drop / consequence analysis should include a dose analysis to personnel involved in the cask movement for the time immediately following the accident. Also, the analysis should address personnel exposure resulting from required entry into plant areas affected by the event and the impact of elevated dose fields on the ability to reach safe shutdown or continue normal plant operation.
(b)
An evaluation addressing the potential for criticality resulting from the postulated cask drop accident scenario described above.
)
(c)
An evaluation that addresses possible means of recovering from the postulated cask drop accident scenario described above.
(d)
An evaluation that addresses whether the potential impact of the scenario described above on other parts of the facility (e.g., the spent fuel pool) is bounded by previous load drop analyses.
This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the Office of Management and Budget, approval number 3150-0012, which expires June 30, 1997. The public reporting burden for this collection of information is covered by the original estimate of 600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> per response for responding to Bulletin 96-02.
The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.
J. Wood Please provide your response within 60 days of your receipt of this request i
for information.
If you need clarification of the staff's request, please contact me at (301) 415-1390.
Sincerely, Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation 1
Docket No. 50-346 cc: See next page 1
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J. Wood Please provide your response within 60 days of your receipt of this request for information.
If you need clarification of the staff's request, please contact me at (301) 415-1390.
t Sincerely,
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Original signed by:
Allen G. Hansen, Project Manager '
Project Directorate III-3 _
Division of Reactor Projects'III/IV Office of Nuclear Reactor Regulation Docket No. 50-346 cc: See next page d
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t To receive e copy of this document, Indcate in the box:
- C" = Copy without enclosures *E' = Copy with enclosures
- N* = No copy 0FFICE PDIII-3:LA l e-PDIII-3:PM_ E l
[i NAME DFoster-Curietn, AHansen fM) l DATE 12/(d96 6f'L 'I2/O /96S '
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i Mr. John K. Wood Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. 1 cc:
4 Mary E. O'Reilly Robert E. Owen, Chief Centerior Energy Corporation Bureau of Radiological Health 300 Madison Avenue Service Toledo, Ohio 43652 Ohio Department of Health j
P. O. Box 118 Mr. James L. Freels Columbus, Ohio 43266-0118 i
Manager - Regulatory Affairs l
Toledo Edison Company c
Davis-Besse Nuclear Power Station Attorney General l
5501 North State - Route 2 Department of Attorney i
Oak Harbor, Ohio 43449-9760 30 East Broad Street Columbus, Ohio 43216 Gerald Charnoff, Esq.
4 l
Shaw, Pittman, Potts Mr. James W. Harris, Director and Trowbridge Division of Power Generation 2300 N Street, N.W.
Ohio Department of Industrial Washington, D.C.
20037 Regulations P. O. Box 825 Regional Administrator Columbus, Ohio 43216 U.S. NRC, Region III 801 Warrenville Road Ohio Environmental Protection Agency Lisle, Illinois 60523-4351 DERR--Compliance Unit ATTN: Zack A. Clayton Mr. Robert B. Borsus P. O. Box 1049 Babcock & Wilcox Columbus, Ohio 43266-0149 Nuclear Power Generation Division 1700 Rockville Pike, Suite 525 State of Ohio Rockville, Maryland 20852 Public Utilities Commission 180 East Broad Street Resident Inspector Columbus, Ohio 43266-0573 U. S. Nuclear Regulatory Comission 5503 N. State Route 2 Mr. James R. Williams Oak Harbor, Ohio 43449 Chief of Staff Ohio Emergency Management Agency Mr. James H. Lash, Plant Manager 2855 West Dublin Granville Road Toledo Edison Company Columbus, Ohio 43235-2206 Davis-Besse Nuclear Power Station 5501 North State Route 2 President, Board of County Oak Harbor, Ohio 43449-9760 Commissioner of Ottawa County Port Clinton, Ohio 43452