ML20084R248

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Forwards Addl Info Re Eight Electrical Components Presently Being Tested to Meet Requirements of NUREG-0588 Per 840413 Request.Util Listing of Electrical Equipment within Scope of 10CFR50.49 Complete & Accurate W/Listed Exceptions
ML20084R248
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 05/14/1984
From: Kammer D
TENNESSEE VALLEY AUTHORITY
To: Adensam E
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8405220249
Download: ML20084R248 (2)


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TENNESSEE VALLEY AUTHORITY CHATTANOOG A.' TENNESSEE 37401 400 Chestnut Street Tower II May 14, 1984

. Director of Nuclear Reactor Regulation Attention:

Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission t

l Washington, D.C.

20555 i

Dear Ms. Adensam:

i In the Matter of

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Docket No. 50-327

-Tennessee Valley Authority

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References:

(1)

L. M. Mills' letter to'you dated March 23, 1984 (2)

L. M. Mills' letter to you dated April 13, 1984 1-(3)

L. M. Mills' letter to you dated April 13,-1984 (4) My letter to you dated May-20, 1983 l'

At the request of Carl Stahle of your staff, L. M. Mills' letter to you dated April 13, 1984 committed TVA to evaluate its listing of electrical equipment within the scope of 10 CER 50.49 and provide within 30 days a l

reconfirmation that the listing is complete and accurate. As requested, TVA has now completed a review of its listing for equipment on unit 1, I

and we have identifjed eight additional components which are presently being tested to meet the requirements of NUREG-0588 and; therefore, have not been completed within the requirements of 10 CFR 50.49. The following enclosure provides additional information on these components.

To the best of_our knowledge with.the exception of these eight items, j

TVA's listing of electrical equipment within the scope of 10 CFR 50.49 is now complete and accurate for Sequoyah unit 1.

l If there are any questions,-please get in touch with R. H. Shell'at l

-FTS 858-2688.

Very truly yours, l'

i TEIGIESSEE VALLEY AUTHORITY 8405220249 840514 p $.

l-PDR ADOCK 05000327 i

P PDR

D..S.,Kammer

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Nuclear Engineer y

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' Sworn d subsor bed before me this day oF 1984.

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$4Y l fb Notary Publia 4g l.

My Commission Expires /"./ -

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.E Nuclear Regulatory Commission (Enclosure) 4 Region II' d

Attn

.Mr. James P. O'Reilly,' Regional Administrator

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g 101' Marietta Street, NW, Suite 2900

.g Atlanta, Georgia 30303 l'

' An Equal Opportunity Employer

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c' ENCLOSURE m

NCR EEB8307, EE58203 The eight components listed below are the steam generator level control valves installed on the auxiliary feedwater system.

It was determined in late 1982 that the valve positioners (which convert a current signal to a pressure signal) on each of these air-operated valves lacked sufficient documentation to verify that they were qualified for the environmental conditions that could occur during certain accidents. Following this, TVA was unable to locate a qualified replacement positioner and finally concluded that this was the best available positioner.

Subsequently, these positioners were entered into a testing program to verify their quallrication.

This created further delays because of the time required to procure positioners from the manufacturer fbe testing.

Initially the positioner was subjected to an accident simulation test to temperatures in excess of 3250F, which is greater than the device would encounter during an accident condition. The performance of the positioner was satisfactory during this test; however, to qualify the positioner to 323-1974 requirements completely, a long-term thermal aging, radiation, seismic, and subsequent LOCA test must be performed. - This testing is still in progress and will not be completed until March 1985.

Justifications for continued operations (JCOs) were provided to you in our letter dated July 20, 1983, ror these components.

In addition, a similar I/P transducer which is installed on the auxiliary feedwater bypass level positioner (Masonellan model 8005A) control valves has been fully qualified by testing.

TVA believes the JCOs submitted to you are still applicable.

Additionally, there is no indication at this time that the positioners in question will not pass the complete quallrication testing program. Based on TVA's evaluation of all available information, we believe these positioners will function as intended. The following components are affected.

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LCV 14 8, 156, 164, 171, 172, 173, 174, and 175.

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