ML20245B398

Discusses Technical & Safety Concerns Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels at Plant

ML20245B398
Person / Time
Site:	Browns Ferry, Sequoyah, 05000000
Issue date:	05/08/1989
From:	Buggs E AFFILIATION NOT ASSIGNED
To:	Zech L NRC
Shared Package
ML20245B391	List: ML20245B388 ML20245B398 ML20245B405 ML20245B408 ML20245B409 ML20245B410 ML20245B412 ML20245B418
References
NUDOCS 8906230157
Download: ML20245B398 (4)

Text

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409 Cameron Circle #.2402

-Chattanooga, TN 37402

May 8,11989-

"MrE Lando.Zech,. Chairman-U.

S. Nuclear 1 Regulatory Commission L

~

c Washington,LD. C.-

20555

Dear Mr-. Zech:

I This lettercisiin reference to several technical and safety

^

'concernsLat Tennessee _ Valley Authority-(TVA) nuclear plants.

The.concer' s were ' submitted to the Nuclear' Regulatory Commission n

sfi (NRC)'in letters of;0ctober 14, 1988; January 19, 1989; Januaryf23, 1989 and' March _10,,1989 (copies enclosed).

.I received W

aireply to my. letters.in a. letter of April 14, 1989 from Ms. Suzanne C.-

?

LBlack, AssistantLDirector-for Projects, TVA Projects Division, Office:of: Nuclear Reactor, Regulation (copy enclosed).

In' reference to the design of sample lines, it is stated in the

'NRC' reply that the design of sample lines'is the responsibility J

of the. licensee.-

Also, the low velocity of the' liquid in the ohotwe11; sampling line is assumed to be satisfactory, and the l

' drawings for the new instrument panels have been' determined to j

I be' correct by TVA..

i

As.you.will noterin my letter of October 14, 1988, I stated that l

'TVA'vas.to-verify that pressure drop and flow calculations were I

performed for panels.

Also, I stated that I has issued five.

Conditions Adverse to Quality Reports (CA0Rs).

In a telephone l

conversation, I~ informed Mr. Paul Cortland, NRC staff, that TVA l

had closed.the-four CA0Rs at' Browns-Ferry Nuclear plant (BFN)

L without' resolving the concerns described.

The four CA0Rs were closedLafter my position had been' eliminated on September 30, 1988.

Accurate _ pressure drop _and flow calculations are particularly j

Limportant for?the reactor _ water cleanup sample panel.at BFN.

ThereLis a glass rotameter with a maximum design pressure of 250 1

pounds-per-square' inch gage (psig) installed on.the sample lines R

used't'o sample high pressure (approximately 1300 psig) reactor water.

-TVA is' relying on a combination of pressure regulators to reduce and' maintain;the pressure'in the sample line.

If~the pressure in the glass rotameter exceeds the maximum design pressure the

? rotameter may burst, causing serious radioactive contamination in the reactor building.

In reference to corrosion inhibitors for closed cooling water systems, the NRC letter of April 14 states that the choice of corrosion inhibitors'for these systems does not fall within the NRC area of_ control.

Some of the systems I. described in my letters of January.~19 and January 23 are required for the safe operation and shutdown of the nuclear reactor.

I would hope that the NRC would verify that~these systems are being properly maintained.

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Finally, the NRC reply'says that the'NRC will not' discuss employment with TVA.

I am not' requesting-~any assistance'from

'the-NRC'as'related to my resuming employment.with TVA.

I submitted.

my concerns to the'NRC to ensure that the items would be resolved and'not simply' ignored since I:was no longer at TVA.

I can-be~ contacted at-615 267-6181 if you require any additional

'information.

Sincerely, Eugene D. Buggs enclosures 1

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