ML19341B159

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Amend 62 to License DPR-20,changing Tech Specs Section 3.5 Re Limiting Condition for Operation for Auxiliary Feedwater Sys & Fire Water Pumps
ML19341B159
Person / Time
Site: Palisades 
Issue date: 10/20/1980
From: Crutchfield D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19341B160 List:
References
NUDOCS 8101300377
Download: ML19341B159 (5)


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,o, i:AITED STATES j

NUCLEAR '<EGULATORY COMMISSION

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E WASHINGTCN, D. C. 20555

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CONSUMERS PCWER CCMPANY DOCKET NO. 50-255 PALISADES PLANT AMEN 0 MENT TO PROVISIONAL OPERATING LICENSE Amendment No. 62 License No. DPR-20 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application by Consumers Power Concany (the licensee) dated July 31,1979, coglies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cogliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the public; E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

8101800 37J 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to read as follows:

"B.

Technical Saecifications The Technical Specitications contained in Appendix A as revised through Amendnent No. 62, are hereby incorporated in the license. The licensee shall operate the f acility in accordance with the Technical Specifications."

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION e'nni s 'K.J.

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C rutchfield, hief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: October 20, 1980 t

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ATTACHMENT TO LICENSE AMENDMENT NO. 62 PROVISIONAL OPERATING LICENSE NO. OPR-20 DOCKET NO. 50-255 Revise the Appendix A Technical Specifications by deleting the folicwing pages and inserting the enclosed pages. The revised pages contain the captioned amendment number and vertical lines reflecting the area of change.

Pages 3-38

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-x Aceli:sbility A;;11es,: the persti:4 status Of the str.a= sad feedvater syste=s.

Ob 'e -ive 7: 1efice certai :: ditices Of ne stes= sad feedvater syste: seces-sssr e a: equate decay test re=0 val.

sa y ::

3:eeif1:sti:.s be tested abcVe 325 ? u=less the f:lMV-351 The primary : cla *, s-=*

ing :::iiti::s are cet; Beta auxilicr/ feeivater pu=ps 0;ersble sed : e fire pu=p :;ersble.

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b.

A mini =;= Of 10C,t:C 62.13 :s Of water in the :: de: sate st:rsge sad pri:1ry : cism: s/ste: =aieu; ta xs :::bi:ed s:: s ba:rup s:=:e Of sediti::a1 vater fre= La.re :41::iss: by the Opersbility

f ::e :f the fire prete:-i:: pu=ps.

All valves, interMexs s:1 piping ass:ciated with the sbeve ::=-

cce
.s required :: f*::-ic ir ing se:ident :: diti::s, are 0;ersble.
i. The :ain stes: st:; valves sre :persbie sud :apable Of :ksics in five se::=ds er less under ::-fhv ::::1-10:s.

3.5 2 '4ith se pri=ary : c;s:: systa= st a, ;e=;ersture greater ::a: 325*?,

the requir.=e::s Of 3 5.1 =ay be :Odified : pe. :.: the f:13 vi:4

litic:s : exis. If ::e syste= is ::: res Orei :: eet the require-

=e :s f 3.51 vi::in he ti=e peri:d spe:ified be2v, the res: cr s-= be pisced i: the ::'1 stu dev :: di.10: vitni: 24 ::= s.

C e suxilis.r/ fee vater pu=; =ay be incpersbie f:r 1 peri:d of s.

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The firevater =akeup to the auxiliary feedvater pu=p suction say be inoperable for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.;.: _If one auxiliary feedwater pump and the firewater makeuo sucoly to the' auxiliary feedwater cumos become inocerable. then tne olant shall be placed in hot standby within I hcur, in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in cold shutdown witnin the'following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3.5.4 With both auxiliary feedwater become inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater cumo to OPEMBl.E status as soon as possible and reduce cower within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the lowest stable power level consistent with reliable main feedwater system operation, a

3-38 Amendment No. 62

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3asts A reseter scu d:v: fre= ; ver requires re::vs1 Of : Ore decay heat.

  • ==ediate decay test reeval require =ents sre ::.-=y satisfied by the stes= by;sss the ::: denser. ?eref:re, : Ore ie:s.* hest :s.

be ::: inueusly dissipated via -he 3,es: by;sss :: the : tie %r ss 1::4 ss feedvater : the sten = geners:Or is sysi'sble. :ic:: ally, the :apabilit/ :: supply feedvater :: the stess genersters

'.s pre-viled by :pers:10: Of the turbine yele feedvater syste=.

1: the u likely event :f ::=plete ':ss ! electricsi ; ver :: the stati::, decsy heat reevtl is by stes: discharge :: the st=cs;:ere via the cais stea= safety valves Or ; ver-c;ersted relief valves.ll,2)

Zitner sun 11ary feedvater pu=; :s: supply suffic us: feedvater for rc *rsi of ie:sy heat fr== the plant. the =i:1== sm:unt of water 1: the ::=densate s :rsge tacks is the a=cus ceeded f:r 3 h:urs of such :perstice.

f the cutage is =:re ths: 3 h:urs, *.ake Micaiss:

vater :s be used, by u-111:i:g a fire ;u=; :: su;;17 vater :: the s=iliar7 feedvater p=; sue:10.

~hree fire pu=ps are pr:vided, 0:e =oter-driven a=d tvo iiesel-driven, each espable Of delivering 15CC g;= s :.25 ;sig. := the eve : si;.

feed pu=;s shou'i be :=e 1: ;ersble, the fire pu=;s eculi be used

p=; isle water :: the stes= genersters 0=ce the see :da.7 pres-sure was reduced sufficie :17 by =eans Of the stes= 1;=; valve. A
1:sure ti=e of 5 see :ds f:r the,a*- stea= s :; valves is :en-sidered siequate and was selected as being :::s; stent vi expected resp: se ti=e f:r instru=ectatica ss detai' ed is -/re s ee= li:e brest incident a:alysis. W

?.eferences

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Amendment No. 62 l

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