IR 05000327/1988036

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Informs That Violation Noted in Insp Repts 50-327/88-36 & 50-328/88-36 Re Type C Testing of Containment Spray Sys & RHR Spray Sys Inboard Containment Isolation Valves Withdrawn
ML20245C790
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 04/24/1989
From: Liaw B
Office of Nuclear Reactor Regulation
To: Kingsley O
TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8904270387
Download: ML20245C790 (5)


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4 UNITED STATES

! k, NUCLEAR REGULATORY COMMISSION '

I b l WASHINGTON, D. C. 20655

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April 24, 1989 l DocketNos.50-32N328

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Mr. Oliver D. Kingsley, Jr.

Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

Dear Mr. Kingsley:

SUBJECT: TYPE C TESTING OF CONTAINMENT SPRAY SYSTEM (CSS) AND RESIDUAL HEAT REMOVAL SPRAY SYSTEM (RHRSS) INBOARD CONTAINMENT ISOLATION VALVES -

INSPECTION REPORT NOS. 50-327/88-36 AND 50-328/88-36 9 cr This is in response to your letter of October 19, 1988, regardingourNoticebf Violation issued on September 16, 1988, concerning activities conducted at yosr Sequoyah facility. The violation was cited due to the failure of TVA to conduct Type C testing for the containment spray system (CSS) and residual heat removal spray system (RHRSS) inboard containment isolation check valves as required by Appendix J of 10 CFR Part 50 or to request an exemption from this testing before July 18, 1988.' Although the violation is valid as written, the NRC has determined that the configuration of the CSS and the RHRSS meet the conditions l for an exemption from Type C testing and that the containment isolation features provided by the current design and your comitments for appropriate testing are l adequate. This decision, which granted the exemption, is documented in our September 22, 1988 response to your August 8, 1988 request for exemption from i the testing requirements for the inboard containment isolation valves.

In light of the above and information presented in TVA submittals since 1986 concerning pertinent containment isolation design issues, the NRC has con-

, cluded that TVA had taken the appropriate steps to meet the containment I isolation requirements of General Design Criteria 56 of 10 CFR Part 50 and I

the administrative requirements of Appendix J, without Type C testing of the inboard check valves. TVA was remiss in not submitting a request for exemption from Appendix J Type C testing of the inboard isolation check valves when it designated them as containment isolation valves prior to issuance of the operating license. However, the NRC has decided to withdraw the violation because (1) discussions which had been ongoing since 1986 between the NRC staff and TVA concerning containment isolation design, including the CSS and RHRSS penetrations and associated Appendix J testing requirements, possibly gave TVA the impression that Type C leak testing Ofol I

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8904270387 890424 PDR h Q ADOCK 05000327 PDC

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M'r. Oliver D. Kingsley, Jr. -2-of the inboard-isolation check valves and an exemption were not required, and (2):the violation is not necessary to ensure effective corrective action.

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l Therefore, Violation ~50-327,328/88-36-01 is withdrawn. 3 We appreciate your cooperation in this matter.

Sincerely, y

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Original signed By B. D. Liaw, Director l TVA Projects Division t Office of Nuclear Reactor Regulation {

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Docket File NRC PDR Local PDR Projects Reading p: ADSP Reading

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DATE :4/ /89 :4/18/89 :4/18/89 :4/18/89 :4/20/89 :4/21/89 0FFICIAL RECORD COPY

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. . ' Mr. Oliver D. ' Kingsley, Jr. - -3- Sequoyah Nuclear Plant cc: .

55 Regional Administrator, Region II LGeneral Counselp .

Tennessee Val)ey Authority U.S. Nuclear Regulatory Comission 400 West Summit Hill Drive 101 Marietta Street, N.W.

E11 B33 .

Atlanta, Georgia 30323 Knoxville, Tennessee .37902 Resident Inspector /Sequoyah NP Mr. C..H. Fox c/o U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road 5N 1578 Lookout Place _

Soddy Daisy, Tennessee 37379 Chattanooga, Tennessee 37402-2801

- Mr. John T. LaPoint- 'Mr. Michael H. Mobley, Director Tennessee Valley Authority Division of Radio'ogical Health Sequoyah Nuclear Plant T.E.R.R. A. Building, 6th Floor P.O. Box 2000 150 9th Avenue North Soddy Daisy, Tennessee 37379 Nashville, Tennessee 37219-5404 Mr. M. Burzynski- Dr. Henry Myers.. Science Advisor.

Tennessee Valley Authority Committee on Interior. :.

' Sequoyah Nuclear Plant and Insular Affairs {

'P.O. Box 2000

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U.S._ House of Representatives s Soddy Daisy, Tennessee 37379 Washington, D.C. 20515 '

Mr. D. L. Williams Tennessee Valley Authority Tennessee Valley Authority Rockville Office-400 West Summit Hill Drive 11921 Rockville Pike W10 B85 Suite 402 Knoxville, Tennessee 37902 Rockville, Maryland 20852 County Judge Hamilton County Courthouse Chattanooga, Tennessee 37402 L

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Mr. Oliver D. Kingsley, Jr. -2 that Type C leak testing of the inboard isolation check valves and an exemption was not required and (2) the violation is not necessary to ensure effective corrective action. Therefore, Violation 50-327,328/88_36-01 is withdrawn.

We appreciate your cooperation in this matter.

Sincerely, B. D. Liaw, Director TVA Projects Division Office of Nuclear Reactor Regulation Distribution Docket File NRC PDR Local PDR Project Reading ADSP Reading DCrutchfield BDLiaw SBlack RPierson LWatson BHayes MSimms JDonohew XSegas CmapuwncA b ( dl N PI dW ^')

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DATE:4/h/89 :4/){/89 :4/ I? 89 :4/1F89 :4/ w /89 :4/ /89 4/y@89 0FFICIAL RECORD COPY

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Mr. Oliver D. Kingsley, Jr. -2-that an exemption was not required and (2) the violation is not necessary to ensure effective corrective action. Therefore, Violation 50-327,328/88-36-01 is retracted.

We appreciate your cooperation in this matter.

Sincerely, i

B. D. Liaw, Director TVA Projects Division Office of Nuclear Reactor Regulation Distribution Docket File NRC PDR Local PDR Project Reading ADSP Reading DCrutchfield BDLiaw SBlack RPierson LWatson BHayes MSimms JDonohew l

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OFFICIAL RECORD COPY