ML20245B388

Responds to 890508 Ltr Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected

ML20245B388
Person / Time
Site:	Browns Ferry, Sequoyah, 05000000
Issue date:	06/15/1989
From:	Liaw B Office of Nuclear Reactor Regulation
To:	Buggs E AFFILIATION NOT ASSIGNED
Shared Package
ML20245B391	List: ML20245B388 ML20245B398 ML20245B405 ML20245B408 ML20245B409 ML20245B410 ML20245B412 ML20245B418
References
NUDOCS 8906230154
Download: ML20245B388 (3)

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JUN 151989 Hr. Eugene D. Buggs:

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Dear Mr. Buggs:

This letter is in reply to your May 8, 1989 letter to Chairma'n Lando Zech, Jr. l of the V. S. Nuclear Regulatory Commission. l In your letter you reiterated your concern that TVA had not fulfilled their agreement to veri.fy that. flow and pressure drop calculations have been performed for the Reactor Water Cleanup-(RWCU) and feedwater and condensate ,

sample panels at the Tennessee Valley Authority's (TVA) Browns Ferry and Sequoyah Nuclear Plants, respectively. In our review of this concern we found that the: sample panels in question are located in non-safety categories of-piping.- Because of this, the sample panel designs have minimal impact on the overall safety of the nuclear power plants and we'have, therefore, developed

. no regulatory concerns in reference to your agreement with TVA. However, TVA has assured us.that post-maintenance testing is in progress to verify that the-sample panel designs will fulfill-their intended functions.

We have researched the dispositions of. the four Condition Adverse to Quality Reports (CAQRs) about which you were concerned. The CAQRs in question were closed at the.TVA offices in Chattanooga, and the technical concerns identified in those CAQRs were initiated as Problem Reporting Documents (PRDs) at Browns Ferry. The actions to remedy the concerns you identified are contained in two engineering change ' notices which are currently scheduled for implementation in September of this year. TVA's' dispositions of these CAQRs were in accordance with their procedures for identifying, reporting, tracking and correcting conditions which may be adverse to quality. As no reactor safety concerns were

. identified in those CAQRs, we have concluded that TVA's actions did not violate NRC regulations, and that the health and safety of the general public and the environment are not affected.

Concerning TVA's selection of a glass rotameter for use in the Browns Ferry Reactor Water Cleanup system sampling line, as well as the associated pressure reducers, our review shows that TVA's design does not violate NRC regulations.

The responsibility for a safe and effective system design belongs to the licensee.

The NRC's role in the design process is one of establishing design and performance criteria which will guarantee the safe operation and shutdown of the nuclear

. reactor. This particular portion of the RWCU system is non-safety related; that i is, it is not relied on to perform any function essential to the safe shutdown of the reactor and to ensure that the general public are not endangered in the event of a plant accident.

8906230154 890615 7 PDR ADDCK 05000259, P PNV p

j. 'Mr. Eugene D. Buggs We have reassessed your. concerns about TVA's selection of corrosion inhibitors

.for closed cooling water systems. Being a chemical engineer, you are aware that the state of the art in the fields of corrosion protection and materials science advance very rapidly. In addition to corrosion prevention effectiveness.

utility management' selection of corrosion inhibitors must include consideration of federal, state, and local environmental and occupational safety and health regulations, equipment design and life expectancy, manufacturer's recommendations, f and cost-benefit trade-offs. As such, it is not feasible for the NRC to specify 4 which corrosion inhibitors must be used by licensees. In response to your concern that the NRC should verify that systems required for the safe operation dnd shutdown of. the nuclear reactor are properly maintained, we must reiterate that although the Commission's range of regulation is generally limited to nuclear safety related and associated systems, the choice of corrosion inhibitors for closed cooling water systems is an issue that does not fall under its area

-of control. We do, however, share the essence of your concern, which is that those systems which are required for the safe operation and shutdown of the nuclear plant must be able to perform their designated safety functions. In this regard, we can assure you that requirements do exist for the periodic inspection and testing of those systems to verify that they can perform their intended safety functions. These requirements are embodied in the Inservice Testing (IST) and Inservice Inspection (ISI) procrams which TVA has implemented at each of their operating nuclear power plants. These programs, which, along with their implementing procedures, have been reviewed by the NRC and are routinely inspected for their proper execution. The IST and ISI programs are developed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, and include equipment performance testing as well as non-destructive examination techniques such as ultrasonic testing, eddy current testing, dye penetrant testing, radiography, pressure testing and visual inspection.

In summary, we find that while your concerns have technical merit, TVA's actions in these matters do not violate NRC regulations. In reference to your concerns, therefore, it is our position that TVA's actions do not have an adverse impact on nuclear reactor safety to the extent that the protection of ,

i the health and safety of the general public and of the environment are affected, We appreciate your interest in nuclear power plant safety.

Sincerely, Original signed by B. D. Liaw, Director TVA Projects Division Office of Nuclear Reactor Regulation

• See Previous Sheet for Concurrence

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