ML20134L649

Forwards Request for Addl Info Re Bulletin 96-02, Movement of Dry Storage Casks Over Spent Fuel,Fuel in Reactor Core,Or Safety-Related Euipment

ML20134L649
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/19/1996
From:	Salehi K NRC (Affiliation Not Assigned)
To:	Hutchinson C ENTERGY OPERATIONS, INC.
References
IEB-96-002, IEB-96-2, NUDOCS 9611210122
Download: ML20134L649 (5)

Text

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l3 UNITED STATES NUCLEAR REGULATORY COMMISSION l

5 WASHINGTON, D.C. 30e06-0001

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/ November 19, 1996

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Mr. C. Randy Hutchinson

{ Vice President, Operations ANO

Entergy Operations, Inc.

! 1448 S. R. 333 Russellville, AR 72801 l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION RELATED TO BULLETIN 96-02,

" MOVEMENT OF DRY STORAGE CASKS OVER SPENT FUEL, FUEL IN THE REACTOR j CORE, OR SAFETY-RELATED EQUIPMENT" - ARKANSAS NUCLEAR ONE, UNIT 1 i

(TAC NO. M96321) <

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Dear Mr. Hutchinson:

The Nuclear Regulatory Commission (NRC) staff has evaluated the responses to j Bulletin 96-02, " Movement of Dry Storage Casks over Spent Fuel, Fuel in the l Reactor Core, or Safety-Related Equipment," and found that some licensees

! without single-failure-proof cranes have analyzed or are planning to analyze j . postulated spent fuel cask and transportation cask drop accidents to establish design basis accidents for their facilities.

i Typical cask drop analyses for in-plant cask movement have analyzed the effects of a drop on plant equipment and/or the impact on cask integrity.

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Those analyses assumed that the cask was in its final condition, its  !

structural lids bolted or welded in place, the fuel remained in the cask at

! all times, and 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 be dropped 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 of the spent fuel elements onto the top of j the spent fuel racks, the floor of the pool, or adjacent areas.

This accident scenario includes the potential for dropping the cask during i movement from the spent fuel pool to the area within the plant building where activities such as drying, inserting, and final securing of the cask lid are i completed. Offsite dose effects are not expected from a cask drop and tip-

! over event in which there is a loss of both the c.ask 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 j plant areas are rendered inaccessible and if operations or maintenance O

,,,u cens *'

9611210122 961119

gDR ADOCK 05000313 ) 'f PDR 1

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l Mr. C. Randy Hutchinson '

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 radiological source term. i 4

Please provide your response to the enclosed questions before cask loading l activities are undertaken. If you need clarification of the staff's request, please contact me at (301) 415-1367.

Sincerely,

~., -

- c Kombiz S hi, Acting Project Manager j Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-313 i

Enclosure:

Request For Additional Information cc w/ enc 1: See next page i

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I

.Mr. C. Randy Hutchinson ,

4 2.

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 radiological source term. ,

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Please provide your response. to the enclosed questions before cask loading 4

activities are undertaken. If you need clarification of the staff's request, please contact me at (301) 415-1367.

l l Sincerely, ORIGINAL SIGNED BY:

+

Kombiz Salehi, Acting Project Manager g Project Directorate IV-1

, Division of Reactor Projects III/IV i Office of Nuclear Reactor Regulation 1 Docket No. 50-313 l

Enclosure:

Request For Additional Information

,- cc w/ enc 1: See next page i DISTRIBUTION:

! fifilef PUBLIC PD4-1 r/f T. Marsh  !

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.~ Roe E. Adensam (EGA1) K. Salehi C. Haughney, NMSS J. Dyer, RIV ACRS OGC (15818) R. Zimmerman 1 C. Hawes W. Beckner W. Reckley l 1

I Document Name: AR96321.RAI *(SEE PREVIOUS CONCURRENCE) 0FC PM/PD4-1 (A)LA/PD4-1 .D/PD3-3 NAME KSalehi/vw CHawes GMarcus*

DATE / /96 / /96 / /96 COPY YES/NO YES/NO YES/N0 OFFICLAL RECORD COPY  !

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*' Note: NMSS/SFP0 & NRR/SPLB concurred on draft PM guidance memo from l which this RAI was taken for early transmittal to ANO I

4 e n ,

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. REOUEST FOR ADDITIONAL INFORMATION

! RELATED TO BULLETIN 96-02. " MOVEMENT OF DRY STORAGE CASKS OVER

-SPENT FUEL POOL" i

ENTERGY OPERATIONS. INC.

l i ARKANSAS NUCLEAR ONE. UNIT 1 DOCKET NO. 50-313 l

i

, To further support Nuclear Regulatory Commissions (NRC) staff evaluation of

{ this potential cask drop scenario, please provide the following:

1. An evaluation of your crane design, load path, and cask loading and unloading processes that determines 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 including 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 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.

ENCLOSURE l

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' Mr. C. Randy Hutchinson Entergy Operations, Inc. Arkansas Nuclear One, Unit 1 cc:

Executive Vice President Vice President, Operations Support l

& Chief Operating Officer Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-199 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 l Jackson, MS 39205 Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing l Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 i

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