ML20117D702

Responds to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety- Related Equipment

ML20117D702
Person / Time
Site:	Vogtle
Issue date:	05/10/1996
From:	Mccoy C GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-002, IEB-96-2, LCV-0814-B, LCV-814-B, NUDOCS 9605140167
Download: ML20117D702 (5)

Text

Georgia Power Company 40 inverness Center Parkway Post Off:ce Box 1295 Birmingham. Alabama 3520t Telephone 205 877-7122 C. K. Mccoy Vce Presdent, Nuclear Georgia Power Vogtle Progx:t May 10, 1996 the southem elecuc system i

LCV-0814-B l

Docket Nos. 50-424  ;

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U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 VOGTLE ELECTRIC GENERATING PLANT RESPONSE TO NRC BULLETIN 96-02 MOVEMENT OF HEAVY L.OADS OVER SPENT FUEL. OVER FUEL IN THE REACTOR CORE. OR OVER S AFETY-RELATED EOUIPMENT Gentlemen:

On April 11,1996, the Nuclear Regulatory Commission (NRC) issued Bulletin 96-02,

" Movement of Heavy Loads Over Spent Fuel, Over Fuelin the Reactor Core, or Over Safety-Related Equipment." The bulletin emphasizes the importance the NRC places on licensee compliance with existing regulatory guidance associated with the control and l handling of heavy loads.

The bulletin requests that licensees review their plans and capabilities for handling heavy j loads in accordance with their licensing basis and existing regulatory guidance (specifically l NUREG-0612, Generic Letter 85-11) This letter provides the NRC requested 30-day response for the Vogtle Electric Generating Plant (VEGP).

, Georgia Power Company (GPC) recognizes the importance of compliance with regulatory l guidance associated with the control and handling of heavy loads at VEGP during all modes of operation. GPC has performed the requested review of plans and capabilities associated with the handling of heavy loads at VEGP Units 1 and 2. The existing implementing procedures at VEGP will be evaluated and strengthened if required by July 19,1996 to assure continued compliance with GPC's accepted response to NUREG-0612 and the Updated FSAR. The movement of heavy loads over safety-related equipment, I which has previously been evaluated, occurs on an as-necessary basis. All licensee actions requested by the bulletin, as appropriate, have been completed. The enclosure to this letter provides a description of these actions.

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GeorgiaPower A U. S. Nuclear Regulatory Commission Page 2 Mr. C. K. McCoy states he is Vice President of Georgia Power Company and is authorized to execute this oath on behalfof Georgia Power Company, and to the best of his knowledge and belief, the facts set forth in this letter are true.

Sincerely, C. K. McCoy Sworn to and subscribed before me this ay [b of h ,1996.

0 471arI Notary APublicA d uu g

! CKM/JLL

Enclosure:

Response to NRC Bulletin 96-02 cc: Georuia Power Company Mr. J B. Beasley, Jr.

Mr. M. Sheibani NORMS U. S. Nuclear Regulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. L. L. Wheeler, Licensing Project Manager, NRR Mr. C. R. Ogle, Senior Resident Inspector, Vogtle 4

4 LCV-0814-B

ENCLOSURE VOGTLE ELECTRIC GENERATING PLANT RESPONSE TO NRC BULLETIN 96-02 Backuround On April i 1,1996, the Nuclear Regulatory Commission (NRC) issued Bulletin 96-02,

" Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or Over Safety-Related Equipment." The bulletin emphasizes the importance the NRC places on licensee compliance with existing regulatory guidance associated with the control and handling of heavy loads and was issued in response to concerns raised by the NRC staff with respect to 10 CFR 50.59 justification of spent fuel storage cask handling at the Oyster Creek Nuclear Power Plant by GPU Nuclear Corporation.

NRC Reauired Response (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 Specification will be required.

(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.

(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 safety-related equipment as a result of a load drop.

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O RESPONSE TO NRC BULLETIN 96-02 (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 changes to Technical Specifications will be required in order to allow the handling of heavy 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.

GPC Response Georgia Power Company responded to NUREG-0612 referenced in the bulletin during the plants construction phase. The complete, systematic evaluation of all overhead load handling equipment for VEGP Units 1 and 2 performed by GPC in accordance with the guidance given in NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants" is described in the Updated FS AR.. In June 1985, the NRC issued an SER to GPC which stated that GPC had satisfied the requirements of Phase I and Phase II of the referenced NUREG.

A review of the VEGP current heavy loads movement program in response to the bulletin indicates that no significant changes have been made to the program and that Updated FSAR section 9.1.5 continues to comply with NUREG-0612.

A detailed description of GPC's response to the required items (1) through (4) above is provided below:

(1) The design and operation of the installed VEGP heavy loads equipment meets NUREG-0612 requirements. Plant procedures administratively control the movement of heavy loads with the reactor at poiver. These plant procedures will be evaluated and strengthened if required by July 19,1996 to assure continued compliance. These activities remain within the scope of the licensing basis for VEGP. All activities involving the handling of heavy loads within the next two years are expected to be within the licensing basis. Therefore, no license amendment request or changes to Technical Specifications are anticipated based on the result of this review.

(2) GPC currently has no plans to implement activities which involve a potential load drop accident not previously evaluated. However, if such an activity were to become l necessary, a license amendment request in advance (6-9 months) of the planned movement will be submitted to allow appropriate review by the NRC.

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a RESPONSE TO NRC BULLETIN 96-02 (3) VEGP is not planning to move dry storage casks over spent fuel, fuel in the reactor i core, or safety-related equipment while the reactor is at power. l l

- (4) Since VEGP currently has no plans to move heavy loads over fuel assemblies in the

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l spent fuel pool while the unit is operating, no changes to Technical Specifications will-be required.

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