ML17339B085

Application to Amend App a of Licenses DPR-31 & DPR-41, Changing Tech Specs,Pages 3.2-2 & 3.2-4,to Reflect Results of Revised ECCS Analysis of Power Distribution Limits for 25% Steam Generator Tube Plugging.Revised Tech Specs Encl

ML17339B085
Person / Time
Site:	Turkey Point
Issue date:	06/05/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17339B086	List: ML17339B085 ML17339B087 ML17339B088
References
L-80-171, NUDOCS 8006090390
Download: ML17339B085 (6)

Text

REGUI.ATORY Il'CARNATION DI'STRISUTION SYSTO (RIDE)

ACCESSION NBR:8006090390 DOCSDATE: 80/06/05 NOTARIZED: NO DOCKElT FACIL:50 250 Turkey Point PlantE Unit 3i F:lorida Power and L.ight C 05000250 50 251 Turkey Point P:lantE- Uni't 4i Florida Power and Light C 05000251 AUTH ~ NAME AUTHOR AFF ILI'A'TI ON UHRIGER,ED Fl;orida Power 8 Light Co ~

REC IP ~ NA'ME RECIPIENT AFFILIATION

SUBJECT:

Application to amend App A of Licenses DPR 31 8 DPR Pii changi:ng Tech SpecsEPages 3 ' 2 8 3 '<<4I to reflect results of rev'ised ECCS analysis on power distribution .limits for DISTR'ISUTION 'CODE: ABOIS TITLE: General

'COPIES RECEIVED:LTR j 25% steam generator tube plugging, Revised Tech Specs encl, ENCL Q Distr.ibut ion for af ter Issuance of SIZE',:

Oper ating Lic NOTES::PQ<Z4M &i@YD~

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME .LTTR ENCL.

CT.ION< 05 BC ORBVr-/ 7 7 NTERNAL:: 01 FILE 1 1 02 NRC PDR 12 I8E 2 2 15 CORE PERF BR 17 ENGR BR 1 1 18 REAC SFTY BR 19 PLANT SYS BR 1 1 20 EEB 21 EFLT TRT SYS OELD 1, 1 1 0

EPB DOR STS GROUP LEADR

,XTERNAL: 03 LPDR 1 1 04 NSIC 23 ACRS 16

~"" 2 0 1989 TOTAL NUMBER OF COPIES REQUIRED'LTTR 38 ENCL 37

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.O. BOX 629100, MIAMI,FL 33162 Jlk~i~AK FLORIDA POWER 8 LIGHT COMPANY June 5, 1980 Office of Nuclear Reactor Regulation L-80-171 Attention: Mr. Darrell G- Eisenhut, Director Division of Licensing U- S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.

Our NSSS vendor (Westinghouse Electric Corp.) has completed a revised ECCS analysis for Turkey Point Units 3 8 4 for a steam generator tube plugging level of 25K. The revised analysis was performed to account for an "upper head" effect that could reduce core cooling during the first few seconds of a LOCA.

The previous analysis assumed that during a LOCA reactor. coolant flow between the upper head region and the core terminates when the reactor vessel level passes below the top of the guide tubes. During the early phase of a LOCA, the upper head fluid enters the core through the control rod guide tube flow holes and retards the normal cooling flow passing upward through the core.

However, flow through the control rod guide tube flow holes is, in fact, expected to terminate when vessel level passes below the upper support plate, which is approximately 3 feet below the top of .the guide tubes. A reduction in the maximum allowed "heat flux hot channel factor" (F ) is required to conservatively accommodate the effect described above.

In performing the revised analysis, the February, 1978 Appendix K,evaluation model was used for the worst DECLG break (CD=0.4), assuming the upper head correction described above, a steam generator tube plugging level of 25$ , a 5X reduction in thermal design flow, and removal of a 65'F fuel temperature conservatism. Our most recently approved ECCS analysis (Amendments 57 and 50 to Operating Licenses DPR-31 and DPR-41, respectively, dated May 15, 1980) was also based on the above assumptions, with the exception of the upper head correction. The current revised analysis 'has been performed at an F of 1.93 for 25K tube plugging with- a resulting PCT of 2171'F. The containmeIIt heat sinks, as shown in Table 3 have been revised to reflect the latest as-built conditions. The detailed results of the analysis are attached.

The proposed amendment is described below and shown on the accompanying this letter in the lower

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Technical Specification pages bearing the date of 1

SO right hand corner.

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Office of Nuc'lear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Di,rector Page Two Pa es 3.2-3 and 3.2-4 Specifications 3.2.6.a (1) and 3.2.6.a(2) are ccmbined to reflect the results of the most recent ECCS analysis on the power distribution limits for a steam generator tube pl'ugging level of 255.

Ol'd Fi ores 3.2-3 3.2-3a and 3.2-3b These figures are no longer applicable and are deleted.

New Fi ure 3.2-3 The normalized hot channel'actor operating envelope for a steam generator tube .plugging level of 25$ is provided to reflect the results of the most recent ECCS analysis.

The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power & Light Company Nuclear Review Board.

They have concluded that it does not involve an unreviewed safety question.

We have determined that since this request involves a single safety issue and a duplicate amendment, the request should be classified as a Class I and a Class I-II amendment pursuant to 10 CFR 170. Accordingly, a check for $ 4,400 is attached.

Very truly yours, o er E. Uhrig Vice President Advanced Systems & Technology REU/le'S/cph Attachments cc: Mr. James P. O'Reilly, Region 'II Harold F. Reis, Esquire

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