ML19319D933

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Proposed Amend 45 to License DPR-54,changing Tech Specs Re Feedwater Chemistry.Tech Specs Encl
ML19319D933
Person / Time
Site: Rancho Seco
Issue date: 10/20/1976
From: Kaplan D, Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML19319D934 List:
References
NUDOCS 8003270609
Download: ML19319D933 (3)


Text

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$ SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 1708 59th Street. Box 15830, Sacramento. Cahfornia 95813;(916) 452 3211

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October 20,/1976 t

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Director of Nuclear Reactor Regulation

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Mr. Robert W. Reid, Chief f y Operating Reactors, Branch 4 2

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Docket No. 50-312 A

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Proposed Amendment No. 45 Rancho Seco Nuclear Generating k'. f.

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Dear Mr. Reid:

In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District hereby proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station, Unit No. 1, by submitting forty (40) copies of Proposed Amendment No. 45.

The attached Proposed Amendment No. 45 is in response to your request to Mr. J. J. Mactimoe dated August 23, 1976.

Rancho Seco Unit I is a pressurized water reactor and utilizes a once-through steam generator with full flow resin demineralization of the feedwater system.

These polisbors nullify any attempt to relate the con-densate to feedwater chemistries.

SMUD does, monitor the cation conductiv-ity of the condensate with inline equipment for early condenser leak detec-tion and more efficient overall plant operation.

SMUD does not consider specifications governing pH or total solids have valid application to the once-through steam generators and full flow polisher '.ystems.

The feedwater pH range of 9.3 to 9.5 is optimum for the carbon steel tubed turbine reheaters.

However, pH variations exist during startup due to a high ammonia concentration of up to 20 ppm during system 11 yup and lower pH conditions are specified if polishing beds are regenerated in hydrogen form. Thus, feedwater pH varies considerably due to operational status and does not provide an indicator of contaminants dettfmental to the steam generator pressure boundary.

The NRC proposed specification for total solids is not a value that can be measured routinely with any degree of accuracy.

Total solids measure-ments are useful as a trending guide and are based on early fossil experience as it i lateu to turbine capacity losses due to deposition.

The value can be estimated from the measured suspended solids and the summation of soluble

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Mr. Robert W. Reid October 20, 1976 material measured, such as silica, copper, etc.

Total solids at low levels must be measured by evaporation of a relatively large sample in a laboratory apparatus and may take.as long as a week to obtain a single measurement.

As a result, total solids do not provide a feasible criteria for controlling feedwater contaminant levels.

Once-through steam generators of the Babcock and Wilcox design have been opertting at six reactors with no indication of corrosion related tube failures.

Three of these facilities have been inspected according to NRC Guide 1.83 with one OTSG being examined twice. These inspections did not show any detectable indication of tube degradation due to corrosion.

Similarly, during visual inspections of the secondary side of the OTSG's, only minimal accumulation of oxide deposits were observed.

Thus,. the present operating criteria have been shown to provide the control necessary to prevent the introduction of corrosive contaminants into the steam generators.

If we can provide additional information please contact us.

Respectfully submitted, SACRAMENTO MUNICIPAL UTILITY DISTRICT By: '

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Q.fl.Mattimoe Assistent General Manager and Chief Engineer 1

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Dajid S. Kaplan' f '

General Counsel (or Sacramento Municipal Utility District Subscribed and sworn to before me this day of October, 1976.

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