ML20009F565
| ML20009F565 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/12/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NCR-CEB-80-12, NUDOCS 8107310308 | |
| Download: ML20009F565 (2) | |
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- Q tir. James P. O'Reilly, Director Offios of Inspection and Enforomaant (1
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Dear 14r. O'Reilly:
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SEQUOYAH If0 CLEAR PLANT ltNIT 2 - liALHORTH VALVB IfEIGHT INCORRECT -
HCR CEB 80 ITVISED FIHl.L PEPORT Ther subject deficiency taas initially reported to HRC-0IC Inspector Plcyd Cabrell on ik ah 13, 1980, in accordance with 10 CPR 50.55(o).
Cncicaed is our revised final report.
Our final report (submitted on April 11, 1940) referenced an incorrect hangar number.
All tradifications have been completed on thLs defiolency.
If you huye any questions, please get in touch with D. L, Lambert at PT3 857-2581.
Very truly yours, TElfM83383 VALLBY AUTHORITY A
L. H.14Lilo,14anager Huolear Regulation and Safety Enclosure Mr. Victor Stello, Director (Enclosure)
REG'CNAL D! RECTOR oct Office of Inspection and Enroccatuant DEPUTY D! RECTOR
.U.S. Nuclsar f;esulatory Counnisalon A"ce:3 TANT TO DIRECTOR Washinston, DC 20555 DIRECTOR, RRPI DIRECTOR, EPOS DIRECTOR, ENF/INV 4
DIRECTOR, ETI ggfl PUBUC AF? AIRS OFFICER g, y e
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8107310308 G10612 PDR ADOCK 05000328 S
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!Ut4UOYAR ffUCI.EM: PLAlfT UNIT 2 EXCZ031YP, FR3S3URE DROP 3 ACROSS Tile CRC 1f STRAINCRS 3QR0-50-328/81
'# 7 10 CPR 50 55(o)
FENAt,HCPORT Descr*1ption of Deficiency During preoperational testing at Sequoyah unit 1, it was discovered t. hat pressure dropa in excess of that designed for existed across t.he ERGf str&iners.
G. P. Kinney Enginewing in Carnegie, Pennsylvania, supplied these strainers and predicted their preacura drop. The act.ual pressura drop, however, was c:uch larger than t.he statad value.
As a result, reduced flow ratuo could occur due co increased syatam posistae Safety Irelications The BRCW System is designed to supply a continuous flow of cooling water to various heat loads in systema and components necessary for clant safety.
As a result of the excussive pres.sure dropa acroas the atrainers, f* Low ratea less rh.vt the values claimed in the plant safet.y unaly Ls could have resulted, which could have adversely affected the safety of the plant.
Correct: Lye /:ctions TVA has roevaluated the total system flow requiramant; and adjusted them downward as dieoussed in NCR SQH3WP8107 and has completed the preoperattaral flow balance test cm the ERCW syatam. The test results indicate the system is capab to of providing the sufficient flcus to the ruain auxiliary buildlnd headers without removing or replecing the strainera, although the flows to certain individual coc:panouts continue to be dat tcient (refer to HCR SQMSVF8107).
Any design modifications t.o the CRCW system emd the required surveillance test prograte will be reported in 1908 SQH H83 803'i etad HCR SQN SWP 8107 Shoulet a nurveillance test prcgram indicate that ecdificaticas to the system ors required, TVA has determin9d that other more effective potential design modificat".ons exist which could eliminate the need to replace, modify, or remove the CRCH ctrataers, While at the same tica, cot:battng the corrosion probbam, l
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