ML20033A527
| ML20033A527 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/17/1981 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20033A524 | List: |
| References | |
| NUDOCS 8111250534 | |
| Download: ML20033A527 (5) | |
Text
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Pn c.
o P 1 RAT 1 o
10uf t t tt.A_**ce gtriP.*. r.uf M
l 8;tyg tyg, a.iw't'l 8 8 8'"
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3 6.t 3y,t,,f,w;g,;
4.6.E det Puer e, 3,6,y Jt t p.-> T2 ec Miteatch b.
The indicated value of care flow rate varies f ro. the-value derived f rca loop flow tireturements by, core.
then 101.
c.
The diffuser to lower plesun dificreistial preenure re..d-ing on an individual jet pump varies ftwo th': s.c a t.
el all jet pwep dif ferce.-
tial pressuree by r. ore that.
lo!.
2.
Whenever there is recirculat.on flow with the teatter is the startup or Run Nede. and cne,.
The reactor sha.u not be circulation punP != operatint 1.
operated with cne recircu'.atica
- 1th the equaliser velve c!r.ed.
loop out. of service for more the diffuser to lower plenu-than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the reactor dif ferential ptersure shall 3 crerat.ity;, if one recireviation checked 4 11; and the differ:n-loop is out of servies, the tial prceaure of an indivi *u al plant shall be placed in a hot jet pump in a luer shall not shutdown conf.itier. within very fron e.he een of 411 jeg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loce is pump a1fferential pressures la sooner returned to seriice, that loop by ester than 1Ct,.
2.
Tollo' ting one pump operr.tlen, y,
y,,
,,,, 73,,gg,,,,,3 the diacharge valve of.the icw speed psirp r.sy riot be opened g,
g,,g,,,g,,g,,,,,,,,,,4,
,,,gg unicas the speed of the f&:,ter be checked and logged at 1 cast 7Jarp !s less thaa "Of. of his
,,,,,,,g,y, rated cpeed.
3.
Steady state operation with both C.
Structural Integrity recirculation pumps pt of ser.
vice for up to 12 hrs is per-mitted. During such interval 1.
Inservice inspection of ASME restart of the recirculation Code Class 1, Class 2, and ournos is oermitted. provided the Class 3 components shall be loop discharge temperature is performed in accordance with within 75 F of the saturation Section XI of the ASME Boiler 0
temperature of the reactor and Pressure vessel Code and vessel water es determined by dome pressure. The total applicable Addenda as required elapsed time in natural circula-by 10 CFR 50, Section 50.55a(g),
tion and o'ie cump oreration must except wherc specific written be no greater than ;'4 nra, relief has been granted by NRC C.
S t'""vral (n,1.;,$I,111 pursuant to 10 CFR 50. Section The 6ttucturnt inter. racy of g gg g g
- 1.
the primary ayeten shall be 182 8111250534 811'117 PDG ADOCK 05000259 P
.i 2avtImE AmRmEm g
U.wI.TISS C0 401ILQ!ti.IOR. R f "A 1.6.C f**"'ceral fa,tfArj y 4.4.C Structural Intearity estateined at the level re-quired by the original accep-tance standards throughout the life of the plant. The reactor chall be maintained in a cold shutdown conditis.n untti each indication of a defect han been investigated r
and evaluated.
4.
Additional inspections shall be performed on certain circunferen-tial pipe velds as listed to pro-vide additional protection aAsinet pipe whip, which could damage auxiliary and control sys-tema.
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CW-9. KFW-13 Feedwater CW-12, CN-26, KFW-31, CFW-29, KFW-39 C N-15, KW -38, and G N-32 CMS-6, KMS-24, Main steam CM5-32, KMS-104 CMS-15, and CKS-24 DSRHR-4, DSRHR-7, RHR D5RHR-6 DSCS-12 DSCS-11 Core Spray DSCS-5, and DSCS-4 18J
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LIMITING CLnamITICIIS 702 OPERATICII SURVEILIECE REQUIRDENTS i
3.6.C Structural Intearity 4.6.c structura" intr;rt:y Reseco -
tlasnup
- 05.WC-4. 33NC-3 D51'iC-6, and D$r4C-5 HPCI - THPCI-70 THPCI-70A THPCI-71, and THPCI-72
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0 4
6 184
.i
-J 4
9 PAGES DE!,ETED 209-214
.s ENCLOSURE 2 JUSTIFICATION AND SAFETY ANALYSIS LICENSE AMENDMENT REQUEST TVA BFNP TS 169 BROWNS FERRY NUCLEAR PLANT UNITS -1 AND 2 (DOCKET NOS. 50-259, -260)
This change to the technical specifications reflects the TVA Inservice Inspection program as it presently exists and as mandated by NRC in'10 CFR 50.55a(g). It does not adversely affect operation, safety margins, accident analysis, or_overall plant safety.
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