ML20072K413

Requests Mod to NRC 830330 Order Confirming Licensee Commitments on post-TMI-related Issues,Allowing Extension for Implementation of NUREG-0737,Item II.B.3, Post-Accident Sampling, to 830901

ML20072K413
Person / Time
Site:	Hatch
Issue date:	06/28/1983
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NED-83-374, TAC-51907, NUDOCS 8307060270
Download: ML20072K413 (2)

Text

Georgia Power Company

• 333 P,edmont Avenue I

v Atlanta. Georgta 30308 Te!ephone 404 526 6526 Ma ting Address Ocst Offrce Ebx 4545 Atlanta. Gecrg a 30302 Georgia Power L T. Gucwa e rn vectnc sy?vm

!* e sourn chef Nuclear Eng:neer Power Generation Department NED-83-374 June 28, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST FOR RELIEF FROM THE SCHEDULE FOR NUREG-0737 ITEM II.B.3 IMPLEMENTATION Gentlemen:

Your letter of March 30, 1983, issued an " Order Confirming Licensee Commitments on Post-TMI Related Issues". That order specified July 1,1983, as the completion date for implementation of NUREG-0737 Item II.B.3 - Post Accident Sampling, as had been proposed in our letter dated March 11, 1983.

It has recently become apparent that we may bc unable to comply with that schedule despite our diligent efforts. Therefore, we hereby request a modification to your March 30, 1983 order to allow an extension in the implementation completion schedule to September 1, 1983.

We have been unable to implement item II.B.3 by the required date for a number of reasons. The underlying cause for the difficulties experienced in projecting and meeting schedules has been the developmental nature of the hardware required to meet the specifications of Item II.B.3. No system was commercially available to perform as specified at the time of the issuance of the requirement. Hence, new design and development was employed in our attempts to provide an adequate solution to the problems posed by Item II.B.3. Consequently, numerous equipment and plant interface problems have occurred which were unforeseen and which have caused delays in implementation. Although tested under shop conditions, the on-line sampling system has yet to be successfully tested in plant. We have made, and will continue to make, a diligent effort to predict and resolve the problems associated with application of new technology, but we are unable to complete the task by the schedule predicted in our March 11, 1983 letter.

Further, a delay of approximately one month occurred in the implementation process which was unanticipated in our earlier schedule estimates. In response to WC Office of Inspection and Enforcement's Enforcement Action 83-35, " Control of Electrical Cable Tray Systems," cable installation for the 8307060270 830628 i PDR ADOCK 05000321 l D

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Georgia Power A Director of NtJclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 June 26, 1983 Page Two Post-Accident Sample System (PASS) was halted on March 18, 1983 and did not resume until personnel training and new administrative controls had been implemented. This resulted in both direct and indirect delays of approximately one month of the allotted time for physical installation of PASS components.

Most recently, during installation testing, several unexpected plant interface problems and a component failure were encountered. The design of the failed component is being reevaluated and modification is likely. The parts potentially necessary for the modification are presently being flown to the plant site; however, this and perhaps other problems yet undetermined will likely prevent operation by July 1, 1983.

Presently, the PASS system is installed and is undergoing functions 1 tests. The uncertainty of the outcome of those tests on this newly designed and unproven PASS, along with the history of problems to date, lead us to request a two-month extension in the implementation schedule. Interim measures for NUREG-0578 post accident reactor coolant and drywell atmosphere sampling, which were established or previously existed, will continue to be available. We believe, therefore, considering these interim measures, the low probability of an accident requiring the PASS to operate, and the basic function of the PASS relative to reactor safety, that this extension request is justified and does not represent any threat to the public health or safety or any degradation in the operational capability of Plant Hatch.

We request your earliest attention to this proposed modification to your March 30,1983 order. If you should have questions in this regard, please contact this office.

Very truly yours,

[E 4e l

L. T. Gucwa WEB /mb l

l l xc: J. T. Beckham, Jr.

l H. C. Nix, Jr.

J. P. O'Reilly (MlC- Region II)

Senior Resident Inspector N0775 u_