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

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:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-77-214
Download: ML18096B486 (10)

Text

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

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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 ~ ~ ~ ~ ~

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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

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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 )

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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

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