ML20059H403
| ML20059H403 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/10/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9009170142 | |
| Download: ML20059H403 (2) | |
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Docket Nos. 50-327-yy',{ Tenne'sseeValley: Authority
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'50-328 1
w u#,..SEQUOYAH. NUCLEAR' PLANTS (SQN) - NRC INSPECTION REPORT. 50-327, 328/86 <.
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1 $j DESIGN (BASELINE AND" VERIFICATION PROGRAM-(DBVP)
DEFICIENCY'D.4.3-3 4
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/DBVPi DeficiencyLD 4.3-3, " Steam Generator Access Platform Design," involve'j d
dl, 7 Unit'. 21ste'amLgenerator. lower supportsL that were.not evaluated for~ permanently 4
,A attached platform: loads;added;by an engineering change notice..-Subsequent l s
a corrective astions:. included' documentation searches, walkdowns'of the supports' i
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to collectTas-built'information about attachments, and a revised structural J
(W*,,; analysis. ' These corrective actions were'~ r'eviewed 'in NRCalnspection; Reporti Nosi 50-327,j382/87-64',. which reported that the prerestart walkdowns~had not:
Yb Lbeen performed in= accordance with TVA'sL quality. assurance requirements.?
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Consequentlyp aicommitment was made by letter dated January 20. 1988, to;
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-reperform! the' ; wall' as :af ter restart by completion of the Unit 21 Cycle.4f b'
Wefuelingiohtase with subscquent confirmatbry structural evaluations by:.
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0 completion of the: Unit?2' Cycle 54 refueling outage.
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'.g lAs the first phas,e'of: work to fulfill the commitment fa'postbestart walkdown5 t
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of' reactor coolant' Loops 1 and~2 was performed during the Unit,2 Cycle'3 j
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' refueling outage. Subsequently, the'as-built information about attachments to Q
l 4 the(lower steam generator' supports collected during the postrestart walkdown 4
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wa's compared to the Loops l and 2 information from the prerestart walkdown.
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b'E As evaluation using the-as -built informat%n from both walkdowns resulted in d
ranLinsignificant. difference:in calculated lower steam generator support.
sloading._!The evaluation concluded.that the prerestart walkdown data for-f
(as low astreasonably achievable) benefit resulting in M
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-saving approximately three person-rems. Consequently, the prerestart walkdown
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information collected for reactor coolant Loops 3 and 4 will be utilized as j
design input for the confirmatory structural evaluation of these lower steam' M
generator supports. The confirmatory structural evaluation will be completed in accordance with the schedule previously committed.
If you have any questjons concerning this submittal, please telephone M
M. A. Cooper at (615) 843-6422.
Very truly yours, 1
TENNESSEE VALLEY AUTHORITY
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hw E. G. Wa lace, Manager Welear Licensing and Regulatory Affairs cc
'Ms. S. C. Black, Deputy Director Project Directorate 11-4 U.S. Nuclear Regulatory Commission One White Flint, North j
11555 Rockville Pike
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.Rockville, Maryland 20852 Mr. J.
.N. Donohew, Project Manager U.S.*Nuc3. ear Regulatory Commission One Whitt Flint, North
-i 11555 Rockville Pike Rockv111t, Maryland 20852 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road 1 Soddy Daisy Tennessee 37379 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II r
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 4
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