1CAN099603, Submits Followup Info Clarifying Permitting Containment Personnel Airlock Doors to Remain Open During Core Alterations

Submits Followup Info Clarifying Permitting Containment Personnel Airlock Doors to Remain Open During Core Alterations

ML20117M899
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/10/1996
From:	Mims D ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1CAN099603, 1CAN99603, NUDOCS 9609180199
Download: ML20117M899 (3)

Text

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e-Entargy Opsrstions, Inc, c-:- EI4TERGY = a 333 Recilac. AR 72801 Tel 501 Bfr3 5000 L

September 10,1996 l'

1CAN099603 U. S. Nuclear Regulatory Conunission Document Control Desk Mail Station PI-137 l Washington, DC 20555 l

Subject:

Arkansas Nuclear One - Unit 1 l Docket No. 50-313 License No. DPR-51

)

Follow-up Information Concerning Open Containment . Personnel Airlock i During Core Alterations Technical Specification Change Request Gentlemen:

i-l By letters dated May 19,1995 (0CAN059503) and June 10,1996 (ICAN069606), Entergy l ' Operations requested changes to the Arkansas Nuclear One, Unit 1 Technical Specifications l permitting the containment personnel airlock' doors to remain open during core alterations. In -

l l a subsequent conversation, the Staff requested clarification be added concerning the closure '

capability of the personnel airlock door. Attached is the revised technical specification page which adds a footnote describing the controls which must be in place in order to ensure the capability to close the door. The conclusions of the no significant hazards consideration of the May 19,1995, submittal remain unchanged by this information. Should you have any further questions, please contact me.  ;

Very truly yours,

' bh W~

l Dwight C. Mims Director, Nuclear Safety DCM/nbm

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9609190199 960910

PDR ADOCK 05000313- i l P PDR '

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( U. S. NRC September 10,1996 1CAN099603 Page 2 i I

cc: Mr. Leonard J. Callan Regional Administrator l U. S. Nuclear Regulatory Commission l l Region IV

!' 611 Ryan Plaza Drive, Suite 400 l . Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One l P.O. Box 310 l

London, AR72847 l.

i l Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2 l -

U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 i i

I

I I , 1.8.6 During tha hindling of irrcdictsd fual in tha rscctor building, at loest one door on the personnel and emergency hatches shall be capable' of p being closed. The equipment hatch cover shall be in place with a minimum l of four bolts securing the cover to the sealing surfaces. At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated within the reactor prersure vessel.

3.8.7 Iselation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be closed.

3.8.8 When two irradiated fuel assemblies are being moved simultaneously by the bridges within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemblies at all times.

3.8.9 If any of the above specified limiting conditions for fuel loading and refueling are not met, movement of fuel into the reactor core shall ceases action shall be initiated to correct the conditions so that the specified limits are net, and no operations which may increase the reactivity of the core shall be made. The provisions of Specification 3.0.3 are not applicable.

3.8.10 The reactor building purge isolation system, including the radiation monitors shall be tested and verified to be operable within 7 days prior to refueling operations. The provisions of Specification 3.0.3 are not applicable.

3.8.11 Irradiated fuel shall not be removed from the reactor until the unit has been suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. In the event of a l complete core offload, a full core to be discharged shall be suberitical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge of more than 70 assemblies to the spent fuel pool. The provisions of Specification 3.0.3 are not applicable.

3.8.12 All fuel har.dling in the Auxiliary Building shall cease upon notification of the issuance of a tornado watch for Pope, Yell, Johnson, or Logan counties in Arkansas. Fuel handling operations in progress will be completed to the extent necessary to place the fuel handling bridge and crane in their normal parked and locked position. The provisions of Specification 3.0.3 are not applicable.

3.8.13 No loaded spent fuel shipping cask shall be carried above or into the Aux!11ary Building equipment shaft unless atmospheric dispersion conditions are equal to or better than those produced by Pasquill Type D stability accompanied by a wind velocity of 2 m/sec. In addition, the railroad spur door of the Turbine Building shall be closed and the fuel handling area ventilation system shall be in operation. The provisions of Specification 3.0.3 are not applicable.

l l 3.8.14 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool. The provisions of Specification 3.0.3 are not applicable.

• Administrative controls shall ensure that appropriate personnel are aware that both l personnel airlock doors are open, a specific individual (s) is designated and available l to close an airlock door following a required evacuation C containment, and any obstruction (s) (e.g., cables and hoses) that could prevent closure of an airlock door be

! capable of being quickly removed.

Amendment No. M, M, M, M,M,M1- 59 l