L-83-460, Application to Amend License DPR-67,changing Tech Specs to Modify Peaking Factors Consistent W/Current Methodology & Unit 2 Tech Specs & Deleting Load Follow Power Peaking Penalties.Safety Evaluation Encl

From kanterella
(Redirected from ML17301A054)
Jump to navigation Jump to search
Application to Amend License DPR-67,changing Tech Specs to Modify Peaking Factors Consistent W/Current Methodology & Unit 2 Tech Specs & Deleting Load Follow Power Peaking Penalties.Safety Evaluation Encl
ML17301A054
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/25/1983
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML17214A413 List:
References
L-83-460, NUDOCS 8308300652
Download: ML17301A054 (5)
v • d • e


Text

REGULATORY FORMATION DISTRIBUTION SY M (RIOS)

AGCESSION NBR:8308300652 DOC~DATKe 83/08/25 NOTARIZEDe YES FACIL:.50 335 St, Lucie Plenty Uni)t 1g Florida 'Power L Light Co.

AUTH ~ BLAME AUTHOR AFFILIATION UHRIGgA ~ E, Florida Power 8 Light Co, AECIP,rCAr>K.

RECIPIENT AFFILIATION EISENHUTrD.G.

Division of Licensing SUBJEKGT: Application,",to amend Lioense DPR 67~changing Tech "Specs to modify peaking.factor's consistent w/current'methodology 8

Unit 2 Terh Specs'

-deleting load follow power peaking penalties. Safety evaluation encl, DISTRIBUTION CODE e A001S COPIES 'RECEIVED jLTR ENCL SIZE'.

TITLE:

OR Submittal:

General Distribution NOTES:

DOCKET 05000335 RECIPIKNT ID CODE/NAME NRA ORB3 BC 01 COPIES I.TTR ENCL" 7

7 RKC IP IENT ID CODE/NAME COPIES LTiTR ENCL INTERNALS ELD/HO82 NRR/DL D IR METB EXTERNALS ACRS NRC PDR NT1'S 00 09 02 1

0 1

1 e

.6 1

1 1

NRR/OK/MTEB NRR/OL/DRAB NRR/OSIS'RAB RGN2 LPOR NSIC 03 05 TOTAL NUMBER OF COPIES REQUIRED:

I'TTR 25 ENCL

?3

l p

1 e

l l>>l>>I>>T

>> c1 J i '<<<<, f,f 1>1><<<<.

1

~

l

<< >II1 ~

rq>>) l <<>>1 l rf1 1<<

s),

~ r l

.p"p g 1 1>> ~r;1pgr 1

C

) >>>>

1 g l 1 <<<<

'4 Ill

'l,>>vp>>p<<1 l

< r 1

<<I pl l

'I <<>>

plCp f r" 1>>>> f

. f

~

c'c'."-

~

<<) $

>>>Jc) de~1

<<,>>n rr>> 1f>>ria I cpI lr1 f1 t am 9 n.p a o u a r lr>>o<<) oooo <<po i l

<<p<<>>g,p r.l Lpf>>,p 1>>

1<<p fl 1'f)

)g<<> f <<'Nc)D

<<'.'10 f 44 f 1 ppr ~c<<'1 r>>n f 1<<) l <<15>>"

<<'.1'1 1<<>

~ 1509 Aor Jt Lp if v'1 g <<

'f>>

1 f l 0 f II>>C>'~

p c l p>>n>>

I

'1 Ill flTJ;

~ )3>>II pi l s <<cl 1<<<<I'I)J 1" <<I<<<<

pgc f 1 1

~ 0 f 1 f <<>> r iIi l Il>'1>>'>><<J<<>>'l f>> 1 l f c! 3 I'<<14 l f ",)

lpl i 1

4 l <<4 l ') ) ) <

pr

'5 l l

<<1 T.p 1

<>i,p,I

,l

<< ~'ltII~ >f)qH>><<<<

' A5ilo>>>> f11'l>>Apl>>

<<<h8 X 1 <<>'(l X>>is<<p'I i.. '>>>>

~ l l I ph

~

l.l 1 lgl cp c'. i l p

9

Office of Nuclear Reactor Regulation Attention:

Hr. Darrell G. Eisenhut, Director Division of Licensing U.

S.

Nuclear Regulatory Commission l/ashington, D.

C.

20555

Dear Nr. Eisenhut:

FLORIDA POWER 5 LIGHT COMPANY August 25, 1983 L-83-460 Re:

St. Lucie Unit 1

'ocket No. 50-335 Proposed License Amendment Pealing Factor and Load Follow Power Peaking Penalty In accordance with 10 CFR 50.90, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A of Facility Operating License DPR-67.

This amendment i s submitted to modify the peaking fac ors (F an@ F<'~

consistent with current methodology.

This revi sion wi 1 1 also make ihe St.

Lucie Unit 1 requirements consistent with St. Luci e Unit 2.

Also, tne load follow power peaking penalties have been removed from Technical Specifications 3.2-1, 3.2-2 and 3.2-3.

The proposed amendment is described below and shown on the accuIIpanying Technical Specification pages.

A safety analyses supporting the removal of the flux peaking augmentation factors have been pr eviously submitted in L 57, dated February 8,

1983.

Page I

The definition listing of load follow operation has been removed.

Page 1-6 The definition of load follow operation has been removed.

Page 3/4 2-2 and 3/4 2-5 The flux peaki ng augmentation factors are not required and the load follow operation uncertainty has been removed.

Page.3/"

2-6 The uncertainty factor 1.03 based removed; Also, the calculational optional use of a full core power

'echnical Specifications.

8308300558 830885 ')

PDR ADDCK 05000335 P. ',,",:,, PDR I,"

on load follow operation for Fx has been T

method for F'

i s modi fied to9e flect xy di stribution analysis consistent with Unit 2 (QQ gk PEOPLE... SERVING PEOPLE

I Office of Nuclear Reac Regulation Attention:

Nr. Darrell G. Eisenhut, Director Page 2

Page 3/4 2-7 and 3/4 2-10 4

The calculational requirements of T have been modified to reflect use of non full core power distribution analysis.

Page 3/4 2-9 The uncertainty factor 1.02 based on load follow operation for FRT has been removed.

Also, the calculational method for FRT is modifi ed to reflect optional use of a full core power distribution analysis consistent with Unit 2

, Technical Specifications.

Page B 3/4 2-1 and B 3/4 2-2 References to load follow operation and the peak flux augmentation factors have been

removed, and the LCO Bases modified to be coincident with St. Lucie Unit 2.

A safety evaluation evaluation and significant hazards evaluation as required by 10 CFR 50.91 and 50.92 is attached.

The proposed.

amendment has been reviewed by the St. Lucie Facility Review G. oup and the Florida Power 8 Light Company Nuclear Review Board.

Very truly yours,

~

~

Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/JEN/j s Attachment cc:

J.

P. O'Reil ly, Region II Harold F. Reis, Esquire

\\I L ~

r l

ttoei I

~

U.a. NUCLEAhhmOULATOhYCOMMISSION es

1. PEE FORM TYPE(ChocaoneI REACTOR FACILITYFEE DETERMINATION INSTR UCTI ON %. FIPMn nemo 1 Ihreegh1 ~, ea OPPICOMO, aroc esne the Onoohal COPy IO Ihe uCenae Fee Managameppt braPCh.

2, DOCKET HUMSEhiSI Fo-3 BS

o. UCENSEE F(.v d

.wcF ~l L S. PLANTNAME ANDUNIT(S)

~RELbaNART FSIAL AMENDED S. ACCE NUMSER g3ot o

e. DATE APPLICATKIH
r. FEEREMITT 0

~. LtCEHSEE FEE OETERMIHATIOH casse I

+ASS ~

CLASS w csass IV class v clA$$ vp sstup.

e SULIECT

10. TACNUMSERASSIONEO(lreveaabrel

~c4v a

wl'1.

APPROVAL Lttr to Ohbth Sass ppopasppt Ipuspes Isa I DATEOF ISSUANCE

12. NRCFEEOETERMIHATIOH The above application hss been reviewed Inaccordance withSection17022 of Part 170 and Is properly Categortted.

The above applkation has been reviewed In accordance withSection 17022 of Part 170 and ls Incorrectly classified.

Fee shouldbe classics):

JUSTIFCATIOHFOR CLASSIFCATNHOR RECLASSIFCATIOH:

Tnlsapplmallonlssclsss lspeolaeoonanelse empllromlessoeoassellls:

Flied by a nonprofit educatknsi Institution.

Filed by a Government agency and ls not fora power reactor.

For a Class I. II, or IIIamendment whkh results from an NRC request dated lor the applkation and the amendmenl Is to slmpil or clarl Ucense or Technksl Specifications: has only minor safety slgnlticance: and ls bel issued for.the convenience of NRC (must meet all of the cr(ter(sf.

Other(Stale reason therefor) n

15. SIGNATURE

'll. FNAL RTIFIGATIDH:Tho bretom loe oatonsinatoonhas boonroasaossou and Is hereby atlprmoo.

SIONATURE (Protect MSPPadet orbreach Cruao FOR LICENSE FEE MANAGEMENTSRANCNUSEONLY(Allofhersdonut wrllebelowfn(a(inc>

The above osemption rocwst has boon rsvNwod aoo Ia hereby occeptoo os being esompt.

SIONATUREfChleLLFlrbl DATE Records Sepvkes brapch DISTRlbUTIONbY LFMb LFMbEsompIIon Fee LFMSReactor Fso

Retrieved from "https://kanterella.com/w/index.php?title=L-83-460,_Application_to_Amend_License_DPR-67,changing_Tech_Specs_to_Modify_Peaking_Factors_Consistent_W/Current_Methodology_%26_Unit_2_Tech_Specs_%26_Deleting_Load_Follow_Power_Peaking_Penalties.Safety_Evaluation_Encl&oldid=5085503"