ML18153A638
| ML18153A638 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/06/1996 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| IEB-96-002, IEB-96-2, TAC-M95593, NUDOCS 9612120293 | |
| Download: ML18153A638 (3) | |
Text
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- UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. J. P~ O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060 December 06, 1996
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2 - 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 Mr. O'Hanlon:
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 actions necessary for safe shutdown with resulting plant damage and in the
'V extent to which the licensee can demonstrate its capability of performing
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presence of a radiological source term.
To support further NRC staff evaluation of this potential cask drop scenario
\\\\/'Iii while the reactor is at power (in all modes other than cold shutdown,
\\Jyv1 refueling, and defueled), please provide the following:
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An evaluation of Ir crane design, 2
load path, and,sk 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)
(b}
(c}
(d}
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 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.
An evaiuation addressing the potential for criticality resulting from the postulated cask drop accident scenario described above.
An evaluation that addresses possible me~ns of recovering from the postu_l ated cask drop accident.scenario described *above.
An evaluation that addresses whether tht 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 tha.t are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501. ef seq.. ). ~These information collections were approved by the Office of Management and Budg¢t, ap*pr;oval ryumber 3150-0012, ~hich 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 Bull et in* ~6-0t.
- Please provide your response whhin :60.day_s of your receipt of.this request for information.
If you need clarification *of :the staff's request, please contact me at (301} 415-1458.,:,.
- Docket Nos. 50-280 and 50-281 cc:
See next page DOCUMENT NAME: G:\\SURRY\\RAI OFFICE PM: PDII~l LA:PDII-1 NAME GEdi son 1{!.
Dunnington
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DATE COPY No
.. *Sint~rely. :.. * * "*
(O:r;iginal Signed By D.. Trimble For)
Gordon E. Edison,* ~r. Project Manager Project Directoiate 11-1 Division of Reactor Projects - 1/11 Office ~f Nucl~ar Reactor R~gulation Distr'ibution:.
Docket File PD IP~ 1 RF PRa SPLB*
D: PDII-1 TMarsh MReinhart 12/02/96 Yes/No Yes/No OFFICIAL RECORD COP
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Mr. J. P. O'Hanlon Virginia Electric and Power Company cc:
Mr. Michael W. Maupin, Esq.
Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. David Christian, Manager Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U.S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta~ Georgia 30323 Robert B. Strobe, M.D., M.P.H.
State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Mr. M. L. Bowling, Manager Nuclear Licensing & Operations Support Innsbrook Technical Center Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060