L-78-297, Supplemental Information on Request to Amend Facility Operating Licenses Additional Information

Supplemental Information on Request to Amend Facility Operating Licenses Additional Information

ML18227D823
Person / Time
Site:	Turkey Point
Issue date:	09/13/1978
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-78-297
Download: ML18227D823 (11)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS >

DISTRIBUTION FOR INCOMING MATERIAL 50-250 5 REC:,STELLO V ORG: UHRIG R E DOCDATE: 09/13/78 NRC FL PWR 5 LIGHT DATE RCVD: 09/20/7:

DOCTYPE: LETTLR NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 3 ENCL 3 FURNISHING ADDL INFO IN SUPPORT OF APPLICANT"S 08/09/78 REQUEST FOR AMEND TO FACILITY OPERATING LIC NOS DPR-31 AND 4li AS A RESULT OF A REEVALUATION OF THE EMERGENCY CORE COOLING SY TEM COOLING PERFORMANCE... W/ATT.+~/+5 PLANT NAME: TURKEY PT 03 REVIEWER INITIAL: X JM TURKEY PT 04 DISTRIBUTER INITIAL:g~

++%+++H+~N+~+4<+ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING I ICENSE.

(DISTRIBUTION CODE A001)

FOR ACTION: BR EF ORB01 BC44W/7'NCL INTERNAL: REG F ~-++W/ENCL NRC PDR~~W/ENCL

~~W/> ENCL OELD+<LTR ONLY HANAUER++W/ENCL CORE PERFORMANCE BR++W/ENCL AD FOR SYS 0 PROJ>+W/ENCL ENGINEERING BR4+W/ENCL REACTOR SAFETY'R+wW/ENCL PLANT SYSTEMS BR<+W/ENCL EEB>>W/ENCL EFFLUENT TREAT SYS+%W/ENCL J MCGOUGH+4W/ENCL EXTERNAL: LPDR S MIAMI FL'++W/ENCL TERA4+W/ENCL NSI C++W/ENCL ACRS CAT B+<W/16 ENCL DISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 780720262 SIZE: 1P+4P THE END

P. O. BOX 013100, MIAMI, FL 33101

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FLORIOA POWER & LIGhT COMPANY September 13, 1978 L-78-297 Office of Nuclear Reactor Regulation Attention: Mr. Victor Stello,, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C; 20555 Dear 'Mr.. Stello=

Re:, Turkey Point Units 3 and Nos. 50-250. and 50-251 4'ocket Proposed Amendment to Facility Operating Licenses DPR-33.. and DPR-41 Additional Information On August 9, 1978,, Florida Power & Light Company requested an amendment to Facility'perating Licenses DPR-31 and'PR-41 as a- result. of a reevaluation of ECCS cooling. performance. (FPL letter L-78'-264).. This revised: ECCS evaluation was performed by Westinghouse using, an evaluation model approved in the in-ternal NRC memorandum,, Safety Evaluation Report on'evised Westinghouse ECCS Evaluation Model dated August 23, 1978 for D. B. Vassallo, Assistant Director for Light Water Reactors, from D. F., Ross,. Assistant Director for. Reactor Safety.

Attached's. Attachment I are the results of 18 case analyses which were performed for the remainder of Turkey Point 3, Cycle 5, (present burnup over 4000 MWD/MTU) and for the upcoming Tur-key Point 4., Cycle 5. These results are being forwarded to you in accordance with a request by a member of your staff. provides information concerning our planned test to be performed following the current refueling outage. 'rogram This information was requested by a member of your staff. revises Table 3 from the Turkey Point Unit 4, Cycle 5 Reload Safety Evaluation, which was submitted to you on June 19, 1978.

Very truly yours, Robert E. Uhrig Vice President REU/GDW/npb 7PO7~O262 PEOPLE... SERVING P OPLE

I ATTACHMENT 1

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A Attachment 2 TABLE 3 TURKEY'OINT 4 - CYCLE 4 AND 5 SHUTDOWN REtlUIREMEHTS AND tiARGINS CYCLE 4 CYCLE 5 BOG BOC EOC Control Rod Worth All Rods Inserted Less Worst Stuck Rod 64 5.89 6. 51 '6.54 (1) Less 10$ 5.08 5.30 5.86 5.89 I

Control Rod Re uirements

'I Reactivity Defects (Doppler, Tav Void, Redistribution) ~

1.76 2.69 2.13 2.70 Rod Inser tion Allowance .70 .70 .50 .50 (2) Total Requirements 2.46 3.39 2.63. 3.20 Shutdown Margin [(1)-(2)] Ahp 2.62 1.91 3. 23 ~

2.69 Required Shutdown Margin (Xhp) 1.00 1.77 1.36- 1.7?

Attachment 3 UNIT 4 CYCLE 5 STARTUP PHYSICS TESTS

1. Control Rod North Acceptance criteria for total measured rod worth is +10%

of design. If the measured rod worth does not meet the calculation of shutdown margin will be made.

criteria, a If shutdown margin cannot be attained, the cause will be determined ancL corrective action taken before power esca-lation begins.

2. Tem erature Coefficient Acceptance criteria: Temperature coefficient is proven negative. If the temperature coefficient is not negative with ARO, a maximum boron will be specified below which the temperature coefficient is negative.

3. HZP FIux Ma and 75% Power Flux Ma Acceptance criteria: A'alculation of peaking factors shall be, made to determine the maximum allowable power level. Values for maximum FhH and FQ must, be less than those specified. in. the- Technical Specifications'o ensure that the assumptions used in the analysis for establishing DNB margin, Linear Heat Rate, and thermal margins "remain valid during operations.

4. ARO Boron Concentration HZP The HZP,. ARO boron concentration acceptance criteria is

+100 ppm of the design value If the acceptance criteria.

cannot be met the cause shall be determined and appropriate action taken to find the deviation.

5. Power Defect The acceptance criteria for the measurement is +10% of the design concentrations value.

shall Ifbe this cannot be met the shutdown boron adjusted for Hot and Cold Shutdown to ensure adequate shutdown margin..