1CAN048701, Application for Amend to License DPR-51,revising Tech Specs to Delete Section 3.8.15 Re Auxiliary Bldg Crane & Associated Basis.Fee Paid
| ML20206K119 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/07/1987 |
| From: | Tison Campbell ARKANSAS POWER & LIGHT CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20206K124 | List: |
| References | |
| TASK-A-36, TASK-OR 1CAN048701, 1CAN48701, GL-85-11, NUDOCS 8704160268 | |
| Download: ML20206K119 (3) | |
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F ARKANSAS POWER & LIGHT COMPANY CAPIT0L TOWER BUILDING /P. O. B0X 551/LITTLE ROCK, ARKANSAS 72203/(501) 377 3525 T. GENE CAMPBELL Vice President Nuclear Operations 1CAN048701 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ATTN:
Mr. J. F. Stolz, Director PWR Project Directorate No. 6 Division of PWR Licensing - B
SUBJECT:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Technical Specification Change Request Regarding the Auxiliary Building Crane
Dear Mr. Stolz:
As you are aware, AP&L is actively participating in the Department of Energy (D0E) Extended Burnup Program.
Part of this program, in association with the ANO-1 fuel vendor, Babcock and Wilcox (B&W), involves the shipment of a maximum of 16 spent fuel pins to the B&W Lynchburg Research Center (LRC) for hot cell examination.
The DOE has made only one licensed spent fuel shipping cask available for a very limited time (April 15 - June 15); therefore, due to this significant schedule constraint we request NRC cooperation in prompt review and approval of this amendment request.
ANO-1 Technical Specification (TS) 3.8.15 presently prohibits handling of a spent fuel shipping cask with the Auxiliary Building crane.
This constraint was made by ANO-1 TS Amendment 17, dated December 17, 1976 (1CNA127641), pending evaluation of the spent fuel cask drop accident and the crane design by AP&L and NRC review and approval. ANO-1 TS Amendment 36, dated October 5, 1978 (1CNA107805), allowed a one time exemption during Cycle 3 to allow the crane to handle a cask for removal and shipment of some irradiated burnable poison rod test assemblies.
The NRC evaluation of this issue was incorporated into the review of the generic issue (A-36) related to control of heavy loads near spent fuel.
On December 22, 1980, the NRC issued NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants"; the transmittal also contained interim actions for implementation and a request for additional information regarding control of heavy loads.
AP&L completed the necessary actions and submittals, and received a Safety Evaluation Report (SER) on October 11, 1984 (0CHA108406) which concluded that Phase I of the issue for ANO-1 & 2 was acceptable.
Completion of Phase II was transmitted by Generic Letter 85-11, dated June 28, 1985 (0CNA068520), which indicated that application for license amendment may be submitted to delete related license conditions citing GL 85-11 as the basis.
This amendment request is therefore submitted to delete TS 3.8.15 and its as ociated Basi.
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_ _ _ _ _ _ _ - _ April 7, 1987 AP&L's procedures, load paths, crane equipment certification and operator training and other related heavy load handling topics were evaluated as part of the control of heavy loads issue and found acceptable.
Spent fuel cask
- ndling is discussed in Section 9.6.2.6 of the ANO-1 SAR.
Specialized equipment is being transferred to ANO by B&W from the Oconee Nuclear Station for removal of the selected individual fuel pins from the extended burnup test fuel assemblies.
This equipment will be set up in the cask pit, the selected fuel pins will be removed and then stored in a special basket in the spent fuel pool.
The equipment will be disassembled and removed from the cask pit, then the shipping cask will be moved into the cask pit and loaded with the basket containing the test fuel pins for shipment.
Preplanning of the fuel pin transfer and related tasks is already well underway, with appropriate considerations based on AP&L's commitment to ALARA principles.
Transportation arrangements, routing, etc. for the shipment are being coordinated by the B&W LRC.
The DOE schedule limitation on the cask has required a tentative shipment date of June 15, 1987.
The circumstances of this proposed TS amendment request are not of an exigent or emergency nature; however, expeditious handling is requested due to the limited availability of the DOE cask, as discussed above.
In accordance with 10CFR50.91(a)(1), AP&L has evaluated the proposed change using the criteria in 10CFR50.92(c) and has d i
~ined that said change involves no significant hazards considerations.
Also, in accordance with 10CFR50.91(b)(1) a copy of this amendment request with attachments has been sent to Ms. Greta Dicus, Director, Division of Radiation Control and Emergency Management, Arkansas Department of Health.
A check in the amount of $150.00 is included herewith as an application fee in accordance with 10CFR170.12(c).
Very truly yours, AWM fx T. Gene Campbel Vice President, Nuclear Operations TGC:RBT Attachments cc:
Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72201
STATE OF ARKANSAS
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sS COUNTY OF PULASKI
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I, T. Gene Campbell, being duly sworn, subscribe to and say that I am Vice President, Nuclear Operations for Arkansas Power & Light Company; that I have full authority to execute this oath; that I have read the document numbered ICAN048701 and know the contents thereof; and that to the best of my knowledge, information and belief the statements in it are true.
AWM-v
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T. Gene Campbel 1
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SUBSCRIBED AND SWORN T0 before me, a Notary Public in and for the County and State above named, this / O day of 1987.
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