ML20043D621
| ML20043D621 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/31/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20043D622 | List: |
| References | |
| TAC-75030, NUDOCS 9006080317 | |
| Download: ML20043D621 (3) | |
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UNITED STATES 0/*'
NUCLEAR RECULATORY COMMISSION
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May 31, 1990 Docket No. S0-327 Mr. Oliver D. Kingsley, Jr.
Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Dear Mr. Kingsley:
SUBJECT:
RELIEF FROM CODE HYDR 0 STATIC PRESSURE TEST REQUIREMENTS FOR REACTOR COOLANTSYSTEM(TAC 75030)-SEQUOYAHNUCLEARPLANT, UNIT 1 By letter dated May 29, 1990, you requested relief from the hydrostatic pressure test requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,1980 Edition through i
the Winter 1981 Addenda (Code). The relief was requested for the reactor coolant system (RCS) and a section of an associated safety injection line of the emergency core cooling system (ECCS) for Unit 1.
The relief is associated with the Unit 1 modification, during the restart from the Cycle 4 t
refueling outage, to replace Check Valve 1-VLV-63-551 in a safety injection line.
You stated that the need to replace the check valve was only recently identified during testing performed to support restart of Unit i from its Cycle 4 refueling outage. Because the replacement and Code weld examination of this check valve is presently scheduled to be completed in the early morning of May 30, 1990 and the unit will then be ready to begin heatup to return to power, you requested that NRC expedite its review of the relief request.
You proposed, as an alternative method to the Code test, to perform a system leakage test of the new valve, welds, and adjoining piping in Mode 3 and a Code examination of the welds.
As discussed in the enclosed Safety Evaluation (SE), the staff has evaluated your request for relief from the Code requirements and concludes that the alternative method of testing proposed by you provides an acceptable level of quality and safety at
-Sequoyah.
Granting relief from Code requirements is authorized by law, pursuant to 10 CFR 50.55a(a)(3)(i), where the proposed alternative to the Code would provide an acceptable level of quality and safety at the plant. Therefore, based on the enclosed SE and pursuant to 10 CFR 50.55a(a)(3)(1), Tennessee Valley Authority is granted the requested relief from the Code for Sequoyah, Unit 1. for the modification to replace Check Valve 1-VLV-63-551, as documented in the enclosed SE.
As you explained, a Code hydrostatic pressure test of the o,
9006080317 900531 PDR ADOCK 050v0327 P
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j Mr. Oliver D. Kingsley, Jr. May 31, 1990 RCS will be performed near the end of the 10. year inservice inspection interval for Sequoyah Unit 1 as part of the Sequoyah inservice inspection program.
Because the staff concluded that the alternative method of testing provides J
an acceptable level of quality and safety and the check valve was scheduled to be replaced in the early morning of May 30, 1990, you were granted the requested relief from the Code on the evening of May 29, 1990.
This letter also documents that this relief was granted on this date.
This relief for the RCS and the associated ECCS piping is in addition to the relief for the RCS granted to Sequoyah by the staff in its letter dated, May 11, 1990 for the modifications in the Cycle 4 refueling outage for each unit to remove the upper head injection system and the RCS resistance tempera.
The Cycle 4 refueling outage for Unit 2 is scheduled to begin in October 1990.
Sincerely.
Original signed by Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
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SEQUOYAH 124
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Mr.' Oliver D. Kingsley, Jr. -
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Mr. Marvin Runyon, Chairman Mr. Joseph Bynum, Acting Site Director Tennessee Valley Authority Sequoyah Nuclear Plant ET 12A 7A Tennessee Valley Authority 400 West Summit Hill Drive P. O. Box 2000 Knoxville, Tennessee 37902 Soddy Daisy. Tennessee 37379 Mr. C. H. Dean, Jr., Director Mr. Mark J. Burrynski Tennessee Valley Authority Site Licensing Manager ET 12A 11A Sequoyah Nuclear Plant 400 West Summit Hill Drive P. O. Box 2000 Knoxville, Tennessee 37902 Soddy Daisy, Tennessee 37379 Mr. John B. Waters, Director County Judge Tennessee Valley Authority Hamilton County Courthouse ET 12A 9A Chattanooga, Tennessee 37402 400 West Sunnit Hill Drive Knoxville, Tennessee 37902 Regional Administrator, Region 11 U.S. Nuclear Regulatory Commission Mr. W. F. Willis 101 Marietta Street, N.W.
Chief Operating Officer Atlanta, Georgia 30323 ET 12B 16B 400 West Summit Hill Drive Mr. Paul E. Harmon Knoxville, Tennessee 37902 Senior Recident Inspector Sequoyah Nuclear Plant General Cuunsel U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou ferry Road 400 West Suminit Hill Drive Soddy Daisy, Tennessee 37379 ET 118 33H Knoxvilie. Tennessee 37902 Mr. Michael H. Mobley, Director Division of Radiological Health Mr. Dwight Nunn T.E.R.R.A. Building, 6th Floor Vice President, Nuclear Engineering 150 9th Avenue North Tennessee Valley Authority hashville, l'ennessee 37219-5404 6N 38A Lookout Place 1101 Market Street Dr. Henry Myers, Science Advisor Chattanooga, Tennessee 37402-2801 Committee on Interior and Insular Affairs Dr. Mark 0. Medford U.S. House of Representatives Vice President and nuclear Washington, D.C.
20515 Technical Director Tennessee Valley Authority Tennessee Valley Authority 6N 38A Lookout Place Rockville Office Chattanooga, Tennessee 37402-2801 11921 Rockville Pike Suite 402 Mr. Edward G. Wallace Rockville, Maryland 20852 Manager, Nuclear Licensing and Regulatory Affairs Tennessee Valley Authority SN 157B Lookout Place Chattanooga, Tennessee 37402-2801 l
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