L-77-214, St. Lucie, Unit 1 - 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

St. Lucie, Unit 1 - 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

ML18096B486
Person / Time
Site:	Saint Lucie
Issue date:	07/07/1977
From:	Uhrig R E Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-77-214
Download: ML18096B486 (10)

Text

gg I2-'7 NRC DISTRIBUTION FoR PART 60 DO U.S.NUCLEAR REGULATORY COMMISSION CKET MATERIAL DOCKET NUMBER 3 3 FILE NUMBER ,TO , g.ETTER P!ORIGINAL CICOPY)DESCRIPTION gNOTORIZED JR UNC LASS I F I E 0 Mr.Victor Stello PROP INPUT FORM ENCLOSU RE FROM: Florida Pwri&Light Company Miami, Florida Robert E9 Uhrig DATE OF DOCUMENT 7/7/77 DATE RECEIVED 7/11/77 NUMBER OF COPIES RECEIVED Amdt.to OL/change o App'hndix A tech specsi~~,notorized

>7/7/77'concerning j sri 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 ECT MANAGER: ICENSING ASS'XSTANT:

ASSIGNED AD: Vo MOORE LTR BRANCH CHIEF: PROJECT MANAGER: LICENSING ASSISTANT:

INTERNAL D STFMS SAFETY HEINEMAN R EDER B9 HARLESS ISTR I BUTION PLANT SYSTEMS TEDESCO BENAROYA SITE SAFETY&ENVIRON ANALYSIS DENTON&MULLER ENGINEERING IPPOLITO OPERATING REACTORS ENVIRO TECH ERNST BALLARD YO G BLOOD VA Zl'ZY CHECK ALT ZLLN TBERG TERNAL DISTRIBUTION BAER BUTLER GRIME GAMMILL 2 SITH ANALYSIS VOLI2KR BUNCH J9 COLLINS KREGER CONTROL NUMBER TIC REG IV J HANCHETT 16 CYS ACRS SENT CAT GO Y NSIC 771930285

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FLORIDA POWER 8I LIGHT COMPANY July 7, 1977 L-77-2l4 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:

e>l I~qi cP~i Re:.St,.Lucie Unit 1 Docket No.50-335 Proposed Amendment to 1'acili~t~

Operas~in License DPR-67'I 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:

x M L 17.0 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 T r (e commission expires: 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 TONDED TNRV t<DhYNARD RONDiNG AGENCY

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