ML20059H403

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Discusses Plant Design Baseline & Verification Program Deficiency D.4.3-3 Noted in Insp Repts 50-327/86-27 & 50-328/86-27.Evaluation Concluded That pre-restart Walkdown Data,Loops 1 & 2 Yielded Adequate Design Input
ML20059H403
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
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

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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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  • U.S. Nuclear Regulatory Commission SEP 101990 f

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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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