View source for L-76-277, Proposed Amendment to Facility Operating License DPR-67. Proposed Change Concerns Technical Specification Concerning an Unfavorable Power Distribution Which Has Led to a Delay in Power Ascension Testing

{{Adams
| number = ML18096B511
| issue date = 07/30/1976
| title = Proposed Amendment to Facility Operating License DPR-67. Proposed Change Concerns Technical Specification Concerning an Unfavorable Power Distribution Which Has Led to a Delay in Power Ascension Testing
| author name = Uhrig R
| author affiliation = Florida Power &amp; Light Co
| addressee name = Stello V
| addressee affiliation = NRC/NRR
| docket = 05000335
| license number = DPR-067
| contact person = 
| case reference number = L-76-277
| document type = Letter type:L, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Safety Evaluation
| page count = 10
}}

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{{#Wiki_filter:U.S. NUCLEAR REGULAT        OMMISSI ON DOCKET NUMBER
[NRC FoRM 195                                                                                               50-335 I2 76)
II                                                                                     FILE NUMBER
              . NRC DISTRIBUTION FoR -PART 50 DOC!(ET MATERIAL TO:                                                     FROM:                                           DATE OF DOCUMENT I                                     Plorida    Power &   Light   Company             7/30/76 Mr R. D. Silver                              Miami, Florida                                DATE RECEIVED Mr. Robert E. Uhrig                              7/30/76 PfJ.ETTE  R                  OTOR  IZED                 PROP                     INPUT FORM             NUMBER OF COPIES RECEIVED OORIGINAL           PKU N C LASS I F I E D one signed copy JRCDE Y DESCRIPTION                                                              ENCLOSURE Ltr. notorized      7/30/76 w/attached.           ~
                                                            ~ .re meeting on 7/29/76 ' ~ .regarding amdt to ol/
change to tech spec, ~ concerning, an unfavorabl power distribution withi'n the Unit 1 reactor core which has led to a delay in power ascension     testing.
ACKNOWLEDGED PLANT NAbfE:                                                                      DO NOT REVIOVE St Lucie 81 SAFETY                                     FOR ACTION/INFORMATION                          8 2 76         RJL ASSIGNED AD:                                                                  ASSI  NED BRANCH    CHIEF:                       Ziemann                                            AD'RO PROJECT 1fANAGER:                                                                      - fANA v LXC 'SSTo:                                 ggs INTERNAL D IST RI BUTION REQ* FIL                         ~
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f Lot!if~4  ~VS-"R 5 'GHT          CGA>PAN'f Ju1y 30, 1976 L-76-277 Director of Nuclear Reactor Regulation Attention: Nr. Victor Stello; Director
                                                                                                                                                                      ".3 cgQ Division of Operating Reactors                                                                                           t'jIff U. S.              Nuclear Regula ory Ccmrais.sion Rashington DC 20553 Dear               r b! .         S   tello:
Re:             St.          I ucie Docket mo. 30-335 Unit              l Proposed Amendment to I. t Xn accordance wi th l0 CF 8 50. 30, Plor ida Power 6 bligh t Company submits here".zi th three (3) signed or iginals arxd forty (40) copies of a request to a:remend Facility Operating License DPR-67                                                                                                               ~
Our z cjiuest is the result of an unfavorable mwer'istribution within the St. tucie Ur>it 1 reactor core whit:h has led to a Our plan for resolving this problem dela>'n go<ver ascension testing,
             @as discussed in a meeting with our staf f or) ~uly 29, l976                                                                                                         ~
The plea inclxrdcs the rerooval of severa3. =uel elements follow~ed TV inspections of the reac+or vessel internals.                                                                                              This will necessit;-a".0 stopping he shutdown cooling water flow whenever the TV carreea is in "hc core. However, Technical Specification
             >.9 8 req4ires "hat; at least one shutdown cooling 3.oop shal3. bc
                       ~
in operation. Therefore, Me reqves t that arx interim license.
amendeant, be granted to waive this ~equi."ernent during the TV inspec" J.ons and to permit. ooeration                                                                     revie'unfed for up to 4 hours without shutdown coolina flaw. A safety evaluation supporting our pro-posal is attached.
The proposed amends.ent has been                                                                                             and the conc3.usion.
reached that                               it       does not invoke.ve a significant hazards consider-,
ation, therefore, prenoticinq pursuant to 10 Cr. R 2.105 should not be requirec'..
Very truly yogrs,                                                                                                          tgIIIfgl8'tg@ Dock8't P(8 Rober            t. E. Uh rig Vice President REU        x HAS: tg Attacbmen cc:              Normal C. Y>osclev 0 act P,. Newman,                                     Esaui r e
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SA" FTY EVAI UATXQ!4 FOR E 277 An    exception is requ~~ ed to Technical Speci fica tion 3.9.8 for the pu=pose of reacto- vessel inspection J.n the ref online triode f Joe to the This     specification requires 3090 gyre shutdo~:n cooling:
("'fGDE 6) .
reac"or vessel at all tirres 'n the refueling mede.
The upcoming core inspection program requires securing of shut--
down cooling flow to the reactor vessel for a fog hour period i
to permit. nspec' Qn 0 C the lo~)'er reactor vessc l This poses no hazard to the health and sa.fety of by r ceo t e means the Public for the fol loving reasons:
: 1. The shutdowns, cooling sys em remains ope able initiation an demand.                               for  jrrmedia"e 2-     The 14Q'i"    RCS  temperature limit in the refueling mode remain in ef feat,. The  present de ay heat load due to a burnup of 800 Y<ND/NTU is much less than the decay heat loading due to a full core cycle bu.nup of 12,806 Nkli3fNTU.
: 3. The 3QQC gpss flo~ requirement is basr d upon the box'on dilution accident as analyzed in Chapter 15 of the FSAR           ~
This accident contains the following assvnptions as a basis:
a ~  All CM's are removed from the coro.
: b. Boron dilution is effected via ',ull low from three charge.zg pusaps.atmaximmn fla~'nject in'rimary di lution Mate." into the reactor vessel for a period of l.5 hours.
: c. ho shutdown cooling flow is present in the core The boron dilution acciden t assumes candi t.ions tooer severe than the conditions which      vill  be present. during the upcosning controlled evolu ion 'ox core inspection. Al3. CEAS's             vill be present in the fuel bundles and not removed fz'oso the core, thus giving at least 5b shutdo~> margin assuming no credit for boron concentra ion in the cooXan". The CVCS flow path bets'een primary dilution w"ate" and the charging pumps he maintained locJ:ed closed under ac'.mSnistra.t,ive control vill dvx'kng this core inspection, thu - eliminating the, dilution mechanism assumed in the accident analysis.

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STATE 0F PLQRXDA ssi CQK;STY OF DADE Rot)ere  E i Uter" 0 bf Snip first col)" swoL'n) Bogoecs 858 sa$ 8 p
That he is a Vice President o Florioa Power E Light Company'<
the iicensee vere'n; That, he has exccut 8 the aforegoing document; t ha" the st.ate-taercts made  in this ski~ docker.t are tme an@ correct to the bes~ oL>> his 3cnovledqe, inZoanaeion, ano he1ie~, and that he is author" @ed, to execu"e he document on behal f of san@
Licensee.
Robert E. Uhrig Subscribers   and sworn     o be~ore me       this HC3     clay o~
NOTARY MBK XC, i.n aiba      or -he County          o     Da    e, 8 ate ok Florida
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