ML17339A721

Forwards Suppl to Proposed Tech Spec Amend to Licenses DPR-31 & DPR-41 Submitted on 770125

ML17339A721
Person / Time
Site:	Turkey Point
Issue date:	03/20/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17339A722	List: ML17339A721 ML17339A723 ML17339A724 ML17339A725
References
L-80-93, NUDOCS 8003240534
Download: ML17339A721 (14)

Text

REGULATORY 'ORMATION DISTRIBUTION SY 9 (RIDS)

SEDATE:

ACCESSION NBR:8003240534 DOC 80/03/20 NOTARIZED: NO DOCKET ¹ FACIL: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'IATION 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 COOK: A001S COPIES RECEIVED: LTR

'ISTRIBUTION ENCI. SIZE!

TITLE: General Distribution for after Issuance of Operating Lic 0 T CC lES4 ~

~ ~~~~~~~~~w~~w&wm~&w&w&w RECIPIENT COPIES RECIPIENT ES ID CODE/NAME Lfl'TR ENCL ID CODE'/NAME LTTR ENCI.

ACTION: 05 BC ~ p gp i 7 7 INTERNAL: 1 02 NRC PDR 1 1 12 I8 17 KNGR BR 19 PLANT SYS BR 2

1 2

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NSIC'OP'I 15 CORE PERF~ BR 18 REAC SFTY BR 20 EKB 1

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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 Harold F. Reis, Esquire II p'E 80 082 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 vs. power method.. Specifically, is grade equipment?

it qualified as safety proposed'T

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

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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.

/