View source for L-77-214, Proposed Amendment to Facility Operating License. Relationship Between Linear Heat Rate & Thermal Power in Specification 4.2.1.3.c Is Revised & Rod Bow Penalty Factor in Specification 4.2.1.4.b Is Deleted

{{Adams
| number = ML18096B486
| issue date = 07/07/1977
| title = Proposed Amendment to Facility Operating License. Relationship Between Linear Heat Rate & Thermal Power in Specification 4.2.1.3.c Is Revised & Rod Bow Penalty Factor in Specification 4.2.1.4.b Is Deleted
| 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-77-214
| document type = Letter type:L, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specification, Amendment
| page count = 10
}}

=Text=
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION        DOCKET NUMBER gg I2-'7                                                                                                          33 FILE NUMBER NRC DISTRIBUTION FoR PART 60 DO CKET MATERIAL
  ,TO                                                  FROM:                                            DATE OF DOCUMENT Florida Pwri & Light        Company                     7/7/77 Mr. Victor Stello                           Miami, Florida                                   DATE RECEIVED Robert E9   Uhrig                                       7/11/77
,  g.ETTER                gNOTORIZED                   PROP                    INPUT FORM               NUMBER OF COPIES RECEIVED P!ORIGINAL         JR UNC LASS I F I E 0 CICOPY
)
DESCRIPTION                                                        ENCLOSU RE Amdt. to OL/change         o App'hndix A    tech specsi ~ ~  ,notorized sri>7/7/77 ' concerning j
the relationship b)tween          linear heat rate and thermal power /Bing revised & the rod bow penalty'actor<being deleted               ~ 9 ~ ~ ~ ~ ~
(2-P)                  (2-P)
PL'ANT NAME: Sti    Lucie Unit      No       1 RJL          7/12/77 FOR ACTION/INFORMATION                      ENVIRHNMENTAL ASSIGNED AD:           Vo MOORE      LTR BRANCH   CHIEF:
ECT MANAGER:                                                 PROJECT MANAGER:
ICENSING ASS'XSTANT:                                             LICENSING ASSISTANT:
B9 HARLESS INTERNAL D ISTR I BUTION STFMS SAFETY                 PLANT SYSTEMS                   SITE SAFETY &
HEINEMAN                          TEDESCO                          ENVIRON ANALYSIS R EDER                    BENAROYA                           DENTON & MULLER ENGINEERING                   IPPOLITO ENVIRO TECH ERNST OPERATING REACTORS                 BALLARD YO G BLOOD BAER VA                             BUTLER                         GAMMILL              2 Zl 'ZY                       GRIME CHECK                                                               SITH ANALYSIS VOLI2KR BUNCH ALTZLLN                                                         J9 COLLINS TBERG                                                        KREGER TERNAL DISTRIBUTION                                              CONTROL NUMBER TIC                                  NSIC 771930285 REG IV J     HANCHETT 16 CYS  ACRS  SENT CAT GO Y

        /t t
r~
  \

FLORIDA POWER 8I LIGHT COMPANY July 7, 1977 L-77-2l4 e>l I~
Director of. Nuclear Reactor Regulation Attention: Nr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

==Dear Nr.      Stello:==
qi cP~i Re:  . St,. Lucie Unit   1 Docket No. 50-335 Proposed Amendment      to 1'acili~t~ Operas~in
                     'I License DPR-67 Zn  accordance with 10 CFR 50.30, Florida Power 6 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License-DPR-67.
The proposed       changes   are described below and shown oa the accompany-ing Technical Specification         page with the date of th~s letter in the lower      right 'hand corner.
Pacae  3/4 2-2 The   relationship between linear heat rate and thermal power in Specification 4.2.1.3.c is revised, and the rod bow penalty factor in Specification 4.2.1.4.b is deleted. This is based on the position developed by our NSSS vendor that, rod bow penalties on linear heat, rate are covered by existing uncertainty factors and that rod. bow penalties on DNB are not required. This position is further supported by the fact.
that rod bow penalties have been deleted from tne Calvert Cliffs technical specifications.
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power 6 Light Company Nuclear Review Board. They have concluded that it does not involve an unreviewed safety question. Please refer to proprietary topical report "77i930285 HELPING BUILD FLORIDA

0 Director of Nuclear Reactor Regulation Page Two CENPD-225-P,   "Fuel and Poison Rod Bowing", October 1976, for a detailed evaluation of rod bowing. The report concludes that no significant rod bow related effects on plant operation are expected   for C-E reactors.
Very   truly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachment cc:    Mr. Norman C. Moseley, Region XX Robert Lowenstein, Esquire

gA POl!ER DISTRIBUTION    LII1ITS SURVEILLANCE RE UIREtlENTS       Continued
: c. Verifying at least      once per 31 days that the THERlSL POWER does not exceed the value determined by the following relationship:
L 17.0     x  M where:
                                                               ~r L is the maximum allowable linear heat rate as determined from Figure 3.2-1 and is based on the core average burnup at the time of the latest incore flux map.
2;    tl  is the  maximum   allowable   THERtQL PO'HER level for the existing Reactor Coolant       Pump  combination.
4.2.1.4    Incore Detector Honitorin S stem - The incore detector moni-toring system may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density'alarms:
: a. Are adjusted= to     satisfy the requirements of the core power distribution     map  which shall be updated at least once per 31 days.
: b. Have  their alarm setpo'int adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately included in the settirg of these alarms:
: 1. Flux peaking augmentation factors as shown in Figure 4.2-1,
: 2. A  measurement-calculational       uncertainty factor of 1.10,
: 3. An   engineering uncertainty factor of 1.03,
: 4. A  linear heat rate uncertainty factor of 1.01        due to axial fuel densification and thermal expansion,
: 5. A THERtiAL PO'HER measurement      uncertainty factor of 1.02.
ST. LUCIE  -  UNIT  1                      3/4 2-2                     7/7/77

STATE OF FLORIDA     )
                             )     ss
                             )
Robert E. Uhrig, being   first     duly sworn, deposes and says:
That he is a Vice President of Florida Power                      &  Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document, are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before          me   this
           /~"    day of NOTARY  PUBLIC,  in and for the        County       of  Dade, State of Florida           >OTARY PURNC STATE OF FLORiDA   ol LARGE 4Y    COh1hRSSlON EXPIRES APRiL  2,  1980 commission expires:     TONDED TNRV t<DhYNARD RONDiNG    AGENCY T
r
(
e

                       ~P I
                            ~-
~g z gg () lAl'J6L l jHA Qh;gcggpg
   ~l":-HA000 03Al3338}}