ML20077Q227

Provides Status of post-accident Sampling Sys & Requests Extension Until 831201 to Implement Schedule Cited in Confirmatory Order,Per NUREG-0737,Item II.B.3.Time Needed Due to Developmental Nature of Hardware

ML20077Q227
Person / Time
Site:	Hatch
Issue date:	09/07/1983
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-83-464, TAC-52320, TAC-52321, NUDOCS 8309160007
Download: ML20077Q227 (3)

Text

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Georg a Pcer Cort pan, 333 P etnont Averae AHant.+. G-orq 4e 30308 Tefechore 404526 M2G W LngAdfev Post Of f ca Box 4545 Asanta. Georga 30VR h

Georgia Power L T. Gucwa t

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i Ct.ef Nuclear Eng %or Poher Generation Departrr+nt September 7, 1983 NED-83-464 Director of Nuclear Reactor Regulation Attention:

Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washirgton, D. C.

20555 NRC DOCKEIS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EIMIN I. HA'ICH NUCLEAR PLANT UNI'IS 1, 2 RECUEST FOR RELIEF FRCM THE SCHEDULE FOR NUREG-0737 ITEM II.B.3 IMPLEMENTATION Gentlemen:

Your letter of July 1, 1983, issued a revision to an " Order Confirming Licensee Commitments on Post 'IMI Related Issues."

'Ihat order specified

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September 1, 1983, as the completion date for implementation of NUREG-0737 Item II.B.3-Post Accident Sampling Capability, as had been proposed in our letter of June 28, 1983.

We were unable to establish full functional capability of the Post Accident Sample System (PASS) by September 1, 1983 despite dililgent efforts and a belief up until that date that the schedule would be met.

These circumstances were discussed with representatives of both the NBC Region II Office of Inspection and Enforcement and the NRC Licensing Project Manager on September 2,

1983.

Pursuant to those conversations, we hereby sutmit a report of the status of PASS capability and a request for revision to December 1,

1983, of the implementation schedule cited in your confirmatory order related to this subject.

As noted in our previous letters on this subject, the underlying cause for the difficulties experienced in projecting and meeting schedules has been the developnental nature of the hardware required to comply with the specifications of Item II.B.3.

No system was comercially available to perform as specified at the time of issuance of the requirement.

Hence, new design and development were employed in our attempts to provide an adequate solution to the problems posed by Item II.B.3.

Consequently, numerous equipnent and plant interface problems have occurred which were unforeseen, and which have required sequential solutions.

This has resulted in costly delays in implementation.

Although tested under shop conditions operated in plant with partial success, the in-lino sampling and analysis system has yet to be successfully fully tested in the plant.

We have made, and will continue to make, a diligent effort to predict and resolve the problems associated with this new application of samplirg technology.

However, we have been unable to complete the task by the schedule predicted in our June 28, 1983 letter.

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Director of Nuclear Reactor kegulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 September 7, 1983 Page Two Presently, the PASS (a shared system between the two units) is installed and has successfully performed a number of its design functions. Correction of problems associated with the as yet non-functional aspects of the PASS are proceeding and will be verified to be corrected by future functional tests.

Specifically, isotopic analyses for both reactor coolant and drywell atmosphere have been successfully completed and confirmed by comparison with laboratory analyses.

Further, the grab sample function has successfully been demonstrated.

Indication of drywell atmosphere hydrogen and oxygen concentration is provided by existing in-line monitors.

Yet to be fully implemented are the on-line analyzers for chlorides, boron, and pH of reactor coolant samples.

%ese analyzers are supplied coolant samples from a pressure reducing subsystem which has failed to function as designed.

The instruments themselves are believed to be operational based upon in-shop testing, but the mechanical problems of pressure reduction and flow control of reactor coolant samples require resolution.

Further, the reactor coolant hydrogen concentration analyzer has exhibited unreliable operation characterized by spurious signals in its electronic signal conditioning circuity.

Efforts in tracing the source of the spurious signals is in progress.

Two of the nonfunctioning chemical analyses (i.e. C1,B) may be performed on-site by use of backup laboratory procedures and the PASS grab sample system.

We reactor coolant hydrogen concentration determination would require off-site laboratory capabilities and might not be available within the time specified by Item II.B.3 criteria.

The pH would be available on-site if sample dilution were not required for personnel radiation exposure considerations.

Otherwise, off-site analysis would be required and possibly not available within three hours.

Additionally, the " interim"

- sanpling capability installed in response to NUREG-0578 requirements remains in effect.

In sununary, the intent of NUREG-0737 Item II.B.3 is believed to have been largely met.

We believe, therefore, considering the present PASS capability, the interim NUREG-0578 measures, the low probability of an accident requiring the PASS to operate, and the basic function of PASS as a monitoring system, that this extension request is justified and does not represent any threat to the public heatlh or safety or any degradation in the operational capability of Plant Hatch.

700775

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'GeorgiaPower A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operatirg Reactors Branch No. 4 September 7, 1983 Page Three We request your attention to this proposed modification to your July 1, 1983 order, and if you should have questions in this regard, please contact this office.

Very truly yours, f,7 Q

-e L. T. Gucwa Manager, Nuclear Engineering and Chief Nuclear Engineer WEB /mb xc:

J. T. Beckham, Jr.

H.' C. Nix, Jr.

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

Eenior Resident Inspector P. D. Rice I

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' 700775

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