ML17339A721

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Forwards Suppl to Proposed Tech Spec Amend to Licenses DPR-31 & DPR-41 Submitted on 770125
ML17339A721
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/20/1980
From: UHRIG R E
FLORIDA POWER & LIGHT CO.
To: EISENHUT D G
Office of Nuclear Reactor Regulation
Shared Package
ML17339A722 List:
References
L-80-93, NUDOCS 8003240534
Download: ML17339A721 (14)


Text

REGULATORY

'ORMATION DISTRIBUTION SY 9 (RIDS)ACCESSION NBR:8003240534 DOC SEDATE: 80/03/20 NOTARIZED:

NO DOCKET¹FACIL:50 250 Turkey Point Plant~Unit 3p Florida Power and L,ight C 05000250 50 251 Tur key Poiint P~lant~Unit 4g F'lor ida Power and Light C 05000251 AUTH'AME AUTHOR AFFIL'IAT ION UHRIGg R~E~F:lorida, Power L Light Co.REC IP~NAME RECIPIENT AFFILIATION EISENHUTiD

~G~D.ivision of Operating Reactors

SUBJECT:

Suppl to proposed Tech Spec amend to L,icenses DPR 31 8 DPR"41 submitted on 770125'ISTRIBUTION COOK: A001S COPIES RECEIVED: LTR ENCI.SIZE!TITLE: General Distribution for after Issuance of Operating Lic ES CC~0 T l 4~~~~~~~~~~w~~w&wm~&w&w&w RECIPIENT ID CODE/NAME ACTION: 05 BC~p gp i INTERNAL: 12 I8 17 KNGR BR 19 PLANT SYS BR 21 KFLT TRT SYS OELD EXTERNAL+03 LPDR , 23 ACRS COPIES Lfl'TR ENCL 7 7 1 2 2 1 1 1 1 1 1 0 1 1 16 16 RECIPIENT ID CODE'/NAME 02 NRC PDR 15 CORE PERF~BR 18 REAC SFTY BR 20 EKB EPB DOR STS GROUP LEADR 04 NSIC'OP'I ES LTTR ENCI.1 1 1 1 1 1 1 1 1 1 1 1 1@lR 8 g 889'OTAL NUMBER OF COP'IES REQUIRED: L~TTR 38 ENCL 37 0 0 f I'i.f l I-i IP,'ll k~'g 4I!1f'l\1 li ht" g-f7 i~J,r-4-~

.BOX 629100, MIAMI, FL 33152~41hz<JA FLORIDA POWER 4 LIGHT COMPANY HaT ch 20, 1980 L-80-93 Office of Nuclear Reactor Regulation Attention:

Mr..Darrell G.Eisenhut, Acting Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.Eisenhut:

Re: TURKEY POINT-UNITS 3 6 4 DOCKET NOS.50-250 6 50-251"hT vs.REACTOR POWER" CURVE The attached information is provided as a supplement to a proposed Technical Specification amendment, which was submitted by letter L-77-32 on January 25, 1977.Very truly yours, Robert E.Uhrig Vice President Advanced Systems 6 Technology REU/MAS/RGM/pa Attachments (3)cc: J.P.O'Reilly, Region II Harold F.Reis, Esquire p'E 8 0 082 40+/5 PEOPLE...SERVING PEOPLE 4i 0 ATTACHMENT 1 Re: TURKEY POINT UNITS 3 6 4 DOCKET NOS.50-250 6 50-251"hT vs.REACTOR POWER" CURVE NRC~~PRELIMINARY REVIEW~~.QUESTIONS 1.Describe, using sketches or drawings as necessary, a].1 the instrumentation used in the existing load vs.flux method.Include channel accuracy,.

calibration frequency and overall curve accuracies.

What section (s)of the FSAR covers this equipment?

2.Does the AT vs.,power curve include flow rate?3.Describe, using sketches or drawings as necessary, all the instrumentation used in the proposed hT vs.power method.Include channel accuracy, location of sensors, cali'bration frequency and overall curve accuracies..

What section (s)of the FSAR covers this equipment?

4'.Describe procedures and calculations used in both methods of this calibration check.Reference the written procedures and logs of this check.5.List.the qualifications of the instrumentation for the proposed'T vs.power method..Specifically, is it qualified as safety grade equipment?

Qi ATTACHMENT 2 Re: TURKEY POINT UNITS 3 6 4 DOCKET NOS.50-250 G.50-25l~."hT vs.REACTOR POWER" CURVF.FPL RESPONSE TO NRC"PRELIMINARY REVIEW" QUESTIONS.To determine backpressuxe one of the two following methods is used: a.Rosemont backpressure s'ensor used to input to plant computer.'Calibration pexformed each refueling.

+.1 in Hg b;Difference between mercury column barometexs measuring condenser vacuum and atmospheric pressure.'+.1 in Hg To determine gross generation:

~Leeds 6 Northrup strip chart recordex.Calibrated at 6 months intervals.

.'+5 HNe.The FSAR does not.address this equipment..

No, the hT vs Power Curve does not.include flow rate..Rosemont,temperature, sensors located in RTD bypass loop, 1 sensor for cold leg and.l for hot leg for each of the RCS loops.Sensors are checked, to be in spec each refueling and are replaced when failed or out of spec.This instrumentation is addressed in'the FSAR, sectin 7.2, pps.1, 12, 20, 21, 27-29 and Figures'7.2-l, 2, 8, and'.-A.Flux Vs.Load,.Gperating'Procedure 12304'.3, Power Range Nuclear Xnstxumentation.Shift Checks and Daily Calibrations..Determine backpxessure irom the difference.

between barometxic pressure and, condenser vacuum ox from'he plant computer.'ead'eactor powex's a function of backpxessuxe and.indicated.

generator load (see attached figures).'The difference.

between calori;metric power and Flux Vs.Load Powex is the coxxection factox for the shift.B.dT Vs.Power This check would be incorporated as an addition to the caloximetric proceduxe (see"A" above).Read reactor power directly as a function of hT.The difference between hT power and calorimetric powex is.the correc-tion factor for the shift.Usi:ng hT.Vs.Power will eliminate secondary system influences related to Flux Vs.Load.The AT instrumentation is safety grade hi

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15-I~4 4~~~~I~f~1~I~I'I~~~I~~~(~~\~i~~~40 60 80 100 120 140 160 180 200 220 240 260 280 , 300 320 340 360.XBO 400 INDICATED LOAD (GROSS GENERATION) 0 ATTACHMENT 3 Re: TURKEY POINT'UNITS 3 8 4 DOCKET NOS.50-'50 8(50-251"aT vs.REACTOR POWER" CURVE The proposed amendment of January 25, 1977 (L-77-32)is attached.

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