View source for L-77-191, 06/23/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/1977

{{Adams
| number = ML18227D843
| issue date = 06/23/1977
| title = 06/23/1977 Letter Request to Amend Appendix a of Facility Operating Licenses. Proposal Submitted to Satisfy Commitment Made in Reportable Occurrence Report 250-77-5 of 05/02/1977
| author name = Uhrig R
| author affiliation = Florida Power &amp; Light Co
| addressee name = Stello V
| addressee affiliation = NRC/NRR
| docket = 05000250, 05000251
| license number = DPR-031, DPR-041
| contact person = 
| case reference number = L-77-191
| document report number = LER 1977-005-00
| document type = Letter type:L, Licensee Event Report (LER)
| page count = 7
}}

=Text=
{{#Wiki_filter:Q/ 8'0/0 U.S. NUCLEAR REGULATORY COMM        N NRC FoRM 195 (2r76 I FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FROM:                                          DATE OF DOCUMENT TO:                                                                                                         6/23/77 Florida Power     &  Light   Company Mr. Victor Stello                       Miami, 'Fla.                                   DATE RECEIVED Robert    ED  Uhrig                                        6/27/77 0 NOTO R IZE D          PROP                    INPUT FORM             NUMBER OF COPIES RECEIVED ETTE R RIG INAL Qcor v UNCLASSIFIED j s/QMM DESCRIPTION                                                      ENCLOSURE Amdt. to OL/change to Appendix A tech specs. ~ ~ . concerns an analysis".per'fermid applicant's            vendor resulting      in
                   +OT PPgQVSi by                  NSSS a  corrected Figure 2 '-1 applicable at the licensed steady state reactor core thermal power output OE 2200 'Mwt         ~ ~ ~ .
lf
                 >CKNOWLEDG@D PLANT NAME:       Turkey Point Units       3 &  A RJL        6/29/77                                (1-P)             (4-p)
FOR ACTION/INFO RM ATI ON                  EI1IRHNMENTAL ASSIGNED AD!          '/ MOORE         LTR BRANCH    CHIEF:
ECT 'YANAGER:                                           PROJECT MANAGER:
CENSING ASSISTANT:                   ALP'Va 5              LICENSING ASSISTS "IT:
B   HARLESS INTERNAL 0 ISTR I BUTION
                                          $ TFMS SAFETY                PLANT SYSTEMS                 SITE SAFETY &
HEINEMAN                      TEDESCO                         ENVIRON ANALYSIS E E                    BENAROYA                         DENTON & MULLER ENGINEERING                 IPPOLITO ENVIRO TECH ERNST OPERATING REACTORS               BALLARD GBLOO BAER VA                            BU ER                         GAMMILL         2 Z CZY CHECK                                                          SITE ANALYSIS VOLLMER AT I                                                           BUNCH LTZMAN                                                       J~ COLLINS BERG EXTERNAL DISTRIBUTION                                             CONTROL NUMBER TIC                               NSIC 771~OOOgD REG  IV J    HANCHETT 16 CYS ACRS SENT CAT      GO NRC FORM 196 I2.76)

FLORIDA POWER 8I LIGHT COMPANY June 23, 1977 L-77-191 Director of Nuclear Reactor Recrulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission washington DC 20555

==Dear Mr. Stello:==
ate      gy. ~ay Re:   Turkey Point Units 3 & 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratinc( Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power & Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-'41.
This proposal is being submitted to satisfy a commitment made in Reportable Occurrence report 250-77-5 of May 2, 1977, (attached). The proposed change is described below and shown on the accompanying Technical Specification page bearing the date of this letter in the lower right hand corner.
Fi ure 2.1-1 An  analysis performed by our NSSS vendor has resulted irr a corrected Figure 2.1-1 applicable at the licensed steady state reactor core thermal power output of 2200 Mwt.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee (PNSC) and the Florida Power
& Light Company Nuc lear Review Board    (CNRB). They have concluded that   it does not involve an unreviewed safety question.
Very   truly  yours, Robert E. Uhrig Vice President REU:HAS:tm Attachments cc: Mr. Norman C. Moseley, Region     ZZ Robert Lowenstein, Esquire                                   77l80004'.)
HELPING BUILD FLORIDA

650 640 2400 PSIA l  630 2250 PSIA I
620 2100 PSIA S
610 I
5   600 P         1900 PSIA
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dl CC 590 580   1700 PSIA 570 560 0  20               60       80     10u       120   ie0 P'" Pc~er   (Percent)
Meta<<o~ Thermal and Hya~vl~c SoFay Lmits Three 4mp Gp   ~)~

4 Fl ORIOA PO TIFA 6 LIGHT COMPANY Nay 2, 1977 PRN-LX-77-131 Ym. Norr an C.      Hoseley.,    Director, Region  XX Office     o=   inspection    ana. Enforcement
~
U. S. Nucl ar Regula.a      o~   Commission K'l.,
230 Peachtree       Street,             Suite 1217 7 tlanta,     Georgia.   "-
Q303

==Dear Hr. hIoseley:==

R    PORTAL= QCCURB"NCE 250-77-5 TUPIK POXNT UHXT 3 DATE OP OCCU ~~ANCE: APRXL 18'g 1977 NOIIXNAL PON R The    attached Licensee.<<vent Report is being submitted in "
accordance with Technical Specification 6.9.2 to provide prompt notification of the subject occurrence.
Very    truly yours, D. Schmidt Vice President Power Resources
         /cpc Att,ach=".ien t CC      Rob'ert Lowens"ein, Esmzire Di e"tor, 0 f'ce of Xnspection and Enforcement (40)
Di ector, 0=fice o Management Xnformation and Prog ~~ Cont ol (3)
PEOPLE... SFP<Vlii4G PLOPLE

LlCEiNSEE EVEiXT REPORT
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See         Paae T=o              fo      co".."===:          ..            o. vent Description and Cause Descri tion.
   ?        9 7
305/552-3802

REPORTASLE OCCURRENCE   250-77-5 LZCENSEE.EVEiiiT REPORT PAGE TWO Event Descri tion (continued) result of the Dnor di,screpancy in Figure 2.1-1. This was the first reportable occurrence at Turkey Point Unit 3 involving a nonconservative specification on reactor core thecal and hydraulic safety limits. A similar report (251-77-3) will be sue='tted for Unit 4.
(250-77-5)
Cause  Descri tion (cc""~- e")        ~ ~
power output. However, they recently advised us that the specific number being used for analytical work was 2192 Mwt. An analysis performed at 2200 Mwt showed that, in a single case,   it wou.d be necessary to make a minor administrative change to a Technical Specifica".ion (Figure 2.1-1). Figure 2.1-1 has been adjusted downward the necesszrv a ount (approximately 1.5'F) to compensate for the correction. A proposed Technical Specification amendment will be submitted to the NRC to request a formal change correcting Figure 2.1-1.}}