ML18012A436

Submits Request for Addl Info Re Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety-Related Equipment

ML18012A436
Person / Time
Site:	Harris
Issue date:	12/05/1996
From:	Le N NRC (Affiliation Not Assigned)
To:	Robinson W CAROLINA POWER & LIGHT CO.
References
IEB-96-002, IEB-96-2, TAC-M95593, NUDOCS 9612090397
Download: ML18012A436 (6)

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@- Yg UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 5,

1996 Mr. W. R. Robinson, Vice President Shearon Harris Nuclear Power Plant Carolina Power 5 Light Company Post Office Box 165 - Hail Code:

Zone I New Hill, North Carolina 27562-0165 SUNECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT I REQUEST FOR ADDITIONAL INFORMATION RELATED TO BULLETIN 96-02, "MOVEMENT OF HEAVY LOADS OVER SPENT

FUEL, OVER FUEL IN THE REACTOR CORE, OR OVER SAFETY-RELATED EQUIPMENT" (TAC M95593)

Dear Hr. Robinson:

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 be also 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.

Offsite 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 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 capability of performing actions necessary for safe shutdown with resulting plant damage and in the presence of a radiological source term.

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:

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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:

Sincerely, (Original Signed By)

Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-400 cc:

See next page DOCUMENT NAME: G:

HARRIS HAR95593.LTR (a)

An analysis of a possible drop of a spent fuel storage or transportation cask involving a drop 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'nalysis 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 sa'fe shutdown or conti'nue normal'plant operation.

- (b)

';Ancevaluation addressing the potential for criticality resulting

"~ from.the~postulate'd cask drop accident scenario described above.

'.'u "'< (c).,,An,',eval.uation",that addresses possible means of recovering from the

,postulated 'cask" drop acci'dent scenario described above.

"=",>., ",' (d)

An evalu'ation'hat addresses whether the potential impact of the scenario'" described, above on other parts of the facility (e.g.,

the spent fu'el" po'ol) is'bounded by,previous load drop analyses.

'his letter.,containrs'infoormation collections that are subject to the Paperwork

.'p Redu'ction'ct 'of o1995

($ 4 cU S.C.

3501 et seq.).

These information collections were-approved by the-'Office of Management and Budget, approval number 3150-

,0012; which expires Ju'ne'0, 1997.

The public reporting burden for this

,collection of information 1s 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 r'esponse for responding to Bulletin 96-02.

Please provide yourresponse 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) 415-1458.

Distribution Docket File PUBLIC PDII-1 RF P.

Ray OFFICE PM: PDI I-1 LA:PDI I-1 SPLB*

D:PDII-1 NAME NLe l~

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Mr. W. R. Robinson Carolina Power

& Light Company Shearon Harris Nuclear Power Plant Unit 1

CC:

Mr. William D. Johnson Vice President and Senior Counsel Carolina Power

& Light Company Post Office Box 1551 Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U.S. Nuclear Regulatory Commission 5421 Shearon Harris Road New Hill, North Carolina 27562-9998 Ms. Karen E.

Long Assistant Attorney General State of North Carolina Post Office Box 629

Raleigh, North Carolina 27602 Public Service Commission State of South Carolina Post Office Drawer 11649

Columbia, South Carolina 29211 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St.,

N.W. Suite 2900 Atlanta, Georgia 30323 Mr. Dayne H. Brown, Director Division of Radiation Protection N.C. Department of Environmental Division of Radiation Protection Commerce

& Natural Resources Post Office Box 27687

Raleigh, North Carolina 27611-7687 Mr. J.

Cowan Vice President Nuclear Services and Environmental Support Department Carolina Power

& Light Company Post Office Box 1551 - Mail OHS7

Raleigh, North Carolina 27602 Mr. Bo Clark Plant General Manager Harris Plant Carolina Power

& Light Company Shearon Harris Nuclear Power Plant P.O.

Box 165 New Hill, North Carolina 27562-0165 Mr. J.

W. Donahue Director of Site Operations Carolina Power

& Light Company Shearon Harris Nuclear Power Plant Post Office Box 165, MC: Zone 1

New Hill, North Carolina 27562-0165 Mr. Robert P. Gruber Executive Director Public Staff NCUC Post Office Box 29520

Raleigh, North Carolina 27626 Chairman of the North Carolina Utilities Commission Post Office Box 29510 Raleigh, North Carolina 27626-0510 Mr. T. D. Walt

Manager, Regulatory Affairs Carolina Power

& Light Company Shearon Harris Nuclear Power Plant P. 0.

Box 165, Mail Zone 1

New'Hill, North Carol ina 27562-0165 Mr. Vernon Malone, Chairman Board of County Commissioners of Wake County P. 0.

Box 550

Raleigh, North Carolina 27602 Ms.

Uva Holland, Chairman Board of County Commissioners of Chatham County P. 0.

Box 87 Pittsboro, North Carolina 27312 Mr. Milton Shymlock U.S. Nuclear Regulatory Comm.

101 Marietta Street, N.W.

.Suite 2900 Atlanta, Georgia 30323-0199

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