ML20063P812

Application to Amend License DPR-57,consisting of Interim Change to Tech Spec Re Maint of Secondary Containment for Period of Upcoming Refueling Outage.Proposed Mod Allows More Efficient Access to Torus Area by Workers

ML20063P812
Person / Time
Site:	Hatch
Issue date:	10/06/1982
From:	Beckman J GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20063P813	List: ML20063P812 ML20063P815
References
TAC-48916, NUDOCS 8210150329
Download: ML20063P812 (3)

Text

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• eu PC'l OFCP UCR 45h MaNa Gi <nga 303T October 6, 1982 GeorgiaPower J. T, Becknam, Jr.

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t. war Gemwan Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 TEMPORARY REVISION TO SECONDARY CONTAINMENT TECHNICAL SPECIFICATIONS Gentlemen:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59 (c)(1), Georgia Power Company (GPC) hereby submits a request for an interim change to the Technical Specifications (Appendix A to the Operating License) for Plant Hatch Unit 1. The proposed change enclosed herein would temporarily revise the Technical Specifications associated with the maintenance of the secondary containment for the period of the upcoming refueling outage. The modifications proposed would allow more efficient access to the torus area by workers and material transfer associated with the massive effort required for the implementation of the Mark I Long-Term l Program. The secondary containment Technical Specifications changes proposed can be accomplished without impact on the public health and safety and would result in significant savings through increased efficiencies in the terus modification work.

i The Unit I secondary containment, as described in paragraph 5.3.3.1 of l the Final Safety Analysis Report, presently encompasses the Unit i reactor l building, as well as the refueling floor area common to Units 1 and 2. We I

propose that the pathways between Unit I reactor building and the refueling floor be closed and sealed and standby gas treatment suctions be realigned such that the Unit I reactor building could be considered independent of the refueling floor from the perspective of secondary containinent. Thus, when conditions exist as proposed in the temporary Technical Specification j

3.7.C.2, the railroad airlock doors into the reactor building could be opened simultaneously while maintaining secondary containment on the pf

refueling floor and conducting refueling operations. The opening of these l railroad airlock doors would allow less restrictive movement of the approximately 350 workers directly involved with the torus work and 650 tons of structural steel and piping which will have to pass in and out of the l reactor building on a routine basis to accomplish the modifications being l made under the Mark I Containment Long-Term

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8210150329 821006 PDR ADOCK 05000321 -

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Georgia Power A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 October 6,1982 Page Two Program. Security controls at the airlock would be enhanced to ensure that no degradation of control-over-access to the reactor building would result.

When conditions other than those specified for the relaxation of secondary containment of the reactor building exist, t% secondary containment will be maintained in accordance with the current pu ' .nent Technical Specifications. Figures 1 and 2 are attacheo .;o aid in understanding the containment definition and valve positions for operation under the permanent and proposed Technical Specifications. Certain temporary plant modifications must be performed to achieve the configuration depicted in Figure 2 and includes, in addition to those modifications discussed above, construction of an airlock for access to the refueling floor, and isolation of a pressure sensor which compares reactor building atmosphereic pressure with outside atmospheric pressure to avoid automatic starts of the standby gas treatment system.

The Plant Review Board and Safety Review Board have reviewed the proposed changes to the Unit 1 Technical Specifications and have concluded that no changes in plant operation are involved and that operation with secondary containment as revised by this submittal will maintain existing margins of safety. Thus, the proposed changes to the Technical Specifications for Unit 1 do not increase the probability of occurrence or consequences of a previously analyzed accident or malfunction of equipment important to safety, nor has the possibility of a previously unanalyzed accident or malfunction of equipment been created. Margins of safety have not been decreased.

As discussed in Attachment 1, the proposed change to the Technical Specifications has been evaluated to be a Class III amendment. Enclosed is-a check for the amendment fee of $4,000.00.

Enclosed are forty (40) copies, including three (3) signed originals, of the proposed Technical Specification changes for your review and approval.

A prompt review is requested in order to allow implementation of the proposed changes to facilitate torus modifications during the refueling outage scheduled to begin October 9,1982.

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Georgia PowerI Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Washington, D. C. 20555 October 6,1982 Page Three Should you have any questions in this regard, please contact this office.

Yours very truly, O h, --

J. T. Beckham, Jr.

JAE/rrb Enclosure xc: 51. C. Nix, Jr.

R. F. Rogers, III J. P. O'Reilly (NRC - Region II) l l

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