ML20009C743
| ML20009C743 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/10/1981 |
| 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, NUDOCS 8107210422 | |
| Download: ML20009C743 (2) | |
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SQRD-50-328/81 PI1!AL REPORT The subject der.toiency was init.ially reported to NHC-02 Inspector
Interin reports wre intbmitted est April 3, April 27, and May 28, 1981.
Cnstased la our final report.
If you have any questioris, please set.tn touch with D. L Lambert at FT5 857-2581, Very truly yours, TDfNICSEE VALLEI AUTHOEITI L. H. Hilla, Hanager*
.5 Woobr.ar Regulatica and Safaby E4fSl@K con it, Viabor Stello, Dimotor (nnalocura)
REGIONAL DIRECTOR Ottico of Inspootton and P.nforcesamt DEPUTY DIRECTOR U.s,Ituel w negnh tory commisalon ASSISTANT TO b'RFC' TOR mhingwi, DC 20555 DIRECTOR, RRPI DIRECTOR, EPCS co (Unalectes):
DIRECTOR, ENF/lN'/
ARas, 640 cst 2-c DIRECTOR, ETI A, E Crevasse, 401 uss-c PUBLIC AFFAIRS OFFir#Rt H. H. Culver, 249A lEB-K E. Ford, Sequoyah-lGIC H. J. Green, 1750 C572-C
%by J. A. Raulston, W10Cl26 C-K H, S. Sanger, Jr., E11833 C-K G. G. St.ack, Sequoyah C00RDIllATED: IN DES /lfeinstein, ifUC PR/SHsehr
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.3%QUOYAH NUCLEAR PLANT UlfiT 2 FLOlf DUICICHUY IN ERCU SYSTCM SQRD-50-326/61-22 10CFMO. 55(e)
PINAL REFOIIT Description of Deficiency During the preoperational teat of the unit 2 CnsentLal Raw Cooling Water Syntam (ERCW) which stem 21atsd the worst operating nase, ubich is unit I in hot standby condition and untt 2 in a pont LOCA condLtion, with the losa of (t) offatte power, (2) downstream dam, and (3) train B diesel generators, the f1w rato requirements to severn1 componenba required for safe shutdown oculd not be inet. The total cystem I'1w rate ruuasured in the test taas approx 11ntely 2,500 spm less than the required design flow inte of 22,000 gpct. A portLon of the flow defiolency cat 2 be attributed to the excessive pressure drop across the strainers, which has been covered by another nonconformance report
)ij (HCR SQMt:I8fl006 R1),
i Saraty Intnlicat. ions The flw deficiencies Ln certain loops of the BRCW Syst.ee indicated a possible inadequacy of tJtose loops' capability to rvimove the specific heat 1 cad requLred of than under the worst condition of two-tu1Lt operation.
Failure to rettove sufficient heat from the corJponents served by the CRQt could result in loss of equipment necessary for a safe shutdown and ultimately in excessiva cora damage, Corrective Action In our last report on thte subject, we stated that unit 2 will nog be operated when the URCW cooling mter inlet t.eeparature exceeda 75 P.
Subsequent reevaluation of the heat loads on various compaenta and cleaning of certatu portions of the piping and equintient have aMowed us to ramove this licLtatt<.m.
Preoperational test results now show that flou to individual cogonsuts is sufficient for the design basis accident with operatton of units 1 and 2 for ERCH cogling water intet tetaperatur e up to the deatsn baats temperAt-uvo of 83 P, TVA is evaluating tire desLgn casts riows to develop flow veraue temper.ature limitaticna for all cogonants.
This data will be used in an inservios curveLilance progenc: being formulated by TVA and for centinued operating guidelines for the plant.
TV4 is alac evaluating the system to identify any additional changes that pould improva the overall performance of the P.RCH sy: stem.
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