ML20033G966
| ML20033G966 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/30/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 9004130201 | |
| Download: ML20033G966 (6) | |
Text
i TENNESSEE VALLEY AUTHORITY s
CH ATTANOOG A. TENNESSEE 37401 L
5N 157B Lookout Place MAR 301990 U.S. Nuclear Regulatory Commission l
ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) - NUREG-0612 - REACTOR VESSEL HEAD (RVH) AND REACTOR VESSEL INTERNALS (RVI) LIFTING DEVICES - ALTERNATIVE TESTING Referenca: TVA letter from L. M. Mills to E. Adensam of NRC dated July 27, 1984, regarding NUREG-0612 The purpose of this letter is to inform NRC of an alternative test method regarding compilance with NUREG-0612 " Control of Heavy loads at Nuclear Power Plants." TVA's original commitment, as contained in the referenced letter, involved the performance of a nondestructive examination (NDE) of the critical load bearing welds on SQN's RVH and RVI lifting devices.
TVA. proposes to use alternative NDE test techniques (i.e., acoustic emission and/or ultrasonics) from those prescribed by NUREG-0612.
TVA finds these alternative NDE techniques to be more practical for the configuration of SQN's lifting l
devices.
TVA's position is that the use of acoustic emission and/or
)
ultrasonics meets the intent of the NUREG-0612 requirements and TVA's original comnit tment.
Enclosure I contains TVA's justification for using the alternative NDE test j
method. contains diagrams of SQN's RVH and RVI lif t devices.
l Please direct questions concerning this issue to Don V. Goodin at (615) 843-7734.
very truly yours, 1
TENNESSLE VALLEY AUlil0RITY l
l E. G. W:11 ace, na Nuclear Liceasing and Regulatory Affairs inclosures cc-See page 2 0
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P PDC An Equal Opportunity Employer
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'8 U.S. Nuclear Regulatory Commission MR801990 cc (Enclosures):
Ms. S. C. Black, Assistant Director
.for Projects.
TVA Projects Division U.S. Nuclear Regulatory. Commission One White Filnt North 11555 Rockville Pike Rockville,-Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA$ Projects Division U.S. Nuc1 car Regulatory. Commission Region II 101 Marietta Street, NW, Suite 2900 1
-Atlanta, Georgia 30323
.NRC Resident Inspector Sequoyah Nuclear. Plant 2600 Igou' Ferry Road Soddy Daisy, Tennessee 37379 f.
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ENCLOSURE 1 NUREG-0612 requires compliance with American National Standards Institute (ANSI) N14.6-1978, Section 5.3.1 to either perform (1) a 10-minute, 150 percent load test of the device in conjunction with a visual inspection for defects and deformation of critical areas and welds or (2) dimensional testing, visual inspection, and nondestructive examination (NDE) of major load carrying welds and critical areas of the device.
TVA originally committed to performing dimensional testing, visual inspection, and NDE of the major load carrying welds as stated in Item 2 above.
This technique is nor considered to be impractical at Sequoyah Nuclear Plant (SQN) for.the following reasons:
1.
A dimensional' test of SQN's tripod lift rig configuration would be inconclusive because of the size, height, and pinned arrangement of the lift devices (14 feet in diameter and 30 feet in height).
Refer to the diagrams provided in Enclosure 2.
2.
Disassembly of tht lifting devices for visual or surface examihatioh would involve a significant hardship and man-hours and could result in alignment probicas where tolerances are critical.
3.
Atl51-N14.6-1978 specifies NDE inspections using liquid penetrant or magnetic particle examination.
These surface examination techniques would.
require removal of paint over the weld surfaces.
Removal of paint has the potential for introducing airborne contamination into the general area.
TVA considers paint removal to be undesirable,for maintaining radiation exposure as= low as reasonably achievable (ALARA).
Proposed Al k iative i
TVA proposes to use acoustic emission testing to locate any active fliws in l
the lift rigs.
Acoustic emission testing will be performed during actual l
lifts of the internals and reactor head.
This will provida dynamic loading of l
the respective lifting during vertical acceleration and normal side swing.
Acoustic emission sensor locatl( is are shown in the diagrams provided in.
The acoustic emission test will be followed by a general sisual examination.
Ultrasonic examination of the pins is planned as an evaluation technique if indications are found from the acoustic emission testing.
The acceptance criteria for the ultrasonic examination will be based on critical flew size calculations and a suitable sensitivity used to detect critical size l.
flaws.
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