ML20117D886
| ML20117D886 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/10/1996 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-002, IEB-96-2, NUDOCS 9605150085 | |
| Download: ML20117D886 (3) | |
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South 2rn Nucisar Op2 rating Company Post Offica Box 1295 Birmingham. Alabama 35201 Telephone (205) 868-5131 Southern Nudear Operating Company o... uor.y Vice President Farley Project the Southem electnc System May 10, 1996 Docket Nos.: 50-348 10CFR50.54(f) 50-364 U. S. Nuclear Regulatory Commission l
ATTN: Document ControlDesk l
Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Response To NRC Bulletin 96-02
" Movement of Heavy Loads Over Spent Fuel, Over Fuel iri the Reactor Core. or Over Safety-Related Equipment" Ladies and Gentlemen:
I On April 11,1996, the NRC issued Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel. Over Fuel in the Reactor Core, or Over Safety-Related Equipment" in order to alert l
utilities to the importance of complying with regulations and the existing regulatory guidelines assos ted with the control and handling of heavy loads while the plant is operating. The NRC l
requested that utilities review their plans and capabilities for handling heavy loads in l
accordance with existing regulatory guidelines and within their licensing basis. The attachment to this letter provides the NRC requested 30-day response for Farley Nuclear Plant (FNP).
l Respectfully submitted, 9605150085 960510
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Mr. S. D. Ebneter, Region II Administrator Mr. B. L. Siegel, NRR Senior Project Manager Mr. T. M. Ross, FNP Sr. Resident Inspector M'
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ATTACHMENT SNC RESPONSE TO NRC BULLETIN 96-02 NRC REOUEST (1) Licensees planning to implement activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment within the next two years must provide, within 30 days of the date of this bulletin, a report that addresses the licensee's review ofits plans and capabilities to handle heavy loads while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled) in accordance with existing regulatory guidelines. The report should also indicate whether the activities are within the licensing basis and should include, if necessary, a schedule for submission of a license amendment request. Additionally, the report should indicate whether changes to Technical Specifications will be required.
SNC RESPONSE Southern Nuclear Operating Company (SNC) has reviewed the plans and capabilities for handling heavy loads while the reactor is at power in accordance with the existing regulatory guidelines and has determined that activities at FNP are within the licensing basis as documented by the NRC Safety Evaluation Report for FNP Control ofHeavy Loads - Phase 1, dated July 25,1984. The review included an evaluation of the licensing correspondence, FSAR and Technical Specifications associated with heavy loads; review of site procedures; a study of the locations of safety-related equipment located under various hoists and cranes in the plant; and discussions with personnel involved with planning, scheduling, maintenance, operations, modifications, core analysis, and training. FNP currently has no plans to move any new extremely heavy loads, such as dry storage casks, over spent fuel, fuel in the reactor core, or safety-related equipment while the plant is operating. Routine maintenance activities involving the lifting of heavy loads over safety-related equipment are performed in accordance with site procedures. No license amendment requests or technical specification changes are necessary at this time.
NRC REOUEST (2) Licensees planning to implement activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled) and that involve a potential load drop accident that has not previously been evaluated in the FSAR, must submit a license amendment request in advance (6-9 months) of the planned movement of the loads so as to afford the staff sufficient time to perform an appropriate review.
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ATTACHMENT SNC RESPONSE TO NRC BULLETIN 96-02 SNC RESPONSE No new activities performed during operations that might involve a potential heavy load drop accident not previously evaluated were identified during the review. No license amendment requests are necessary at this time.
NRC REOUEST (3) Licensees planning to move dry storage casks over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled) include in item 2 above, a statement of the capability of performing actions necessary for safe shutdown in the presence of radiological source term that may result from a breach of the dry storage cask, damage to the fuel, and damage to l
safety-related equipment as a result of a load drop.
l SNC RESPONSE SNC currently has no plans to move dry storage casks over spent fuel, fuel in the reactor core, or safety-related equipment while the plant is operating. The FNP Operating License includes a condition prohibiting the use of the spent fuel cask crane for the purpose of l
moving spent fuel casks prior to approval by the NRC of the lifting devices which attach the spent fuel cask to the crane.
NRC REOUEST (4) Licensees planning to perform activities involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled) must determine whether l
changes to Technical Specifications will be required in order to allow the handling of heavy j
loads (e.g. the dry storage canister shield plug) over fuel assemblies in the spent fuel pool and submit the appropriate information in advance (6-9 months) of the planned movement ofloads for NRC review and approval.
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SNC RESPONSE l
FNP has no plans involving the handling of heavy loads over spent fuel, fuel in the reactor core, or safety-related equipment while the reactor is at power that require a technical specification change.
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