ML18227B248

06/23/1977 Letter Proposed Amendment to Appendix a of Facility Operating Licenses, Concerning Analysis Performed by Applicant'S NSSS Vendor Results Related to Reactor Core Thermal Power Output

ML18227B248
Person / Time
Site:	Turkey Point
Issue date:	06/23/1977
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
LER 1977-005-00
Download: ML18227B248 (12)

Text

/ 8'0/0 NRC FoRM 195

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NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL U.S. NUCLEAR REGULATORY COM F E

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TO: FROM: DATE OF Dg))M)NT Florida Power & Light Company Mr. Victor Stello Miami, Fla, DATE RECEIVED Robert ED Uhrig 6/27/77 0 NOTOR I 2E D PROP INPUT FORM NUMBER OF COPIES RECEIVED S/gM~

ETTE R RIG QCOP Y INAI )REIN C LASS I F I E D j

DESCRIPTION EN CLOSU RE Amdt. to OL/change to Appendix A tech specso ~ 0 concerns an analysisppet'formed by applicant's NSSS vendor resulting in a corrected Figure 2 '-1 applicable at the licensed steady state reactor core thermal power output of 2200 Mwt, ~ ~ ~ ~

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-PL'ANT NAME: Turkey Point Units 3 8

'RJL 6/29/77 (1-P) (4-p)

FOR ACTION/INFORMATION ENVIRHNMENTAL ASSIGNED AD: V~ MOORE LTR BRANCH CHIEF:

ECT MANAGER: PROJECT MANAGER:

ICENSING ASSISTANT: .A.Va ~ 5 LICENSING ASSISTANT:

Bo HARLESS INTERNAL DISTRIBUTION STFMS SAFETY PLANT SYSTEMS SITE SAFETY &

HEINEMAN TEDESCO ENVIRON ANALYSIS ROEDER BENAROYA DENTON & MULLER ENGINEERING IPPOLITO ENVIRO TECH ERNST OPERATING REACTORS BALLARD GBLOOD BAER VA BUTLER GA1&IILL 2 ZT8CZY GRIME CHECK SITE ANALYSIS VOLLMER AT&I BUNCH ALTZMAN Ji COLLINS TBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER TIC NSIC 77iSOOOyy, REG IV J HANCHETT 16 CYS ACRS SENT CAT GO NRC FORM 195 I2.76)

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P. O. BOX OI3100, MIAMI, FLORIDA 3310I

+II//g 8 Jpgge, FLORIDA POWER 8t LIGHT COMPANY all 3~1se~zN June 23, 1977 8 L-77'-191 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, 'Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington DC 20555

Dear Mr. Stello:

Re: 'Turkey Point Units 3 6 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 Light Company S

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.

This proposal is being submitted to satisfy a commitment made in Reportable Occurrence report 250-77-5 of May 2, 1977, (attached). The proposed change is described below and shown on the accompanying Technical Specification page bearing the date of this letter in the lower right hand corner.

Fi ure 2.1-1 An analysis performed by our NSSS vendor has resulted in a corrected Figure 2.1-1 applicable at the licensed steady state reactor core thermal power output of 2200 Mwt.

The proposed .amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee (PNSC) and the Florida Power 6 Light Company Nuc 3ear Review Board (CNRB). They have concluded that it does not involve an unreviewed safety question.

Very truly yours, Robert E. Uhrig Vice President REU:MAS:tm Attachments cc: Mr. Norman C. Moseley, Region II Robert Lowenstein, Esquire 77180004 HELPING SUILD FLOR IDA

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FLORIOA PO'/lEA 5 LIGHT COMPANY May 2, 1977 PRN-LI-77-131 Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement II U. S. Nucl ar Regula~o~ Commission 230 Peachtree Street, K H., Suite 1217 Atlanta, Georgia 39303 Dear Mr. Moseley=

RZPORT~L= OCCURRENCE '250-77-5 TUPWY POINT UNIT 3 DATE OP OCCUBPXNCE: APRIL 18', 1977 NOMINAL POET'R The attached Licensee-Event Report is being submitted in "

accordance with Technical Specification .6.9.2 to provide prompt notification of the subject occurrence.

Very truly yours, D. S chmidt Vice President Power Resources PAS/cpc Attachment cc:- Robert Lowenstein, Escpzire Director, 0 fice of I'nspection and Enforcement (40)

Director, Of=i e o Management Information and Progr~~ Control (3)

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~Ol2 Di l~ ions Mth ou NS S ~endor have shown that Technical S ecification Pi ure 2.l-l 7 a 9

~CI3 "Reactor Core dermal and H draulic Safet Limits" reauizes revision. An analysis 7 99

~Ol I ezformed at 2200 'P~t has vielded. a corrected Pi ure 2 l-l ao licable to both Units 3 6 9 and 4. No chanc'e to seto'oircts. ooeratino limits or ooeratin ractices are re uired 7 = 9 I .IH as a result o= tnis cor acti . - Neither unit has ever operated nonconservativel as a PL4ec C'US= Cph)PC44e4T CCMFCN e)T CahlPCN i~ hl AN4P~)'~

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~ i REPORTABLE OCCURRENCE 250-77-5 LICENSEE.EVENT REPORT PACE TWO Event Descri tion (continued) result of the minor discrepancy in Figure 2.1-1. This was the first reportable occurrence at Turkey Point Unit 3 involving a nonconservative specifi'cation on reactor core tnermal and hydraulic safety limits. A similar report (251-77-3) will be sub '-tted for Unit 4.

(250-77-5)

Cause Descri tion (cc" z e")

power output. However, they recently advised us that the specific number being used for analytical wcrk was 2192 Mwt. An analysis performed at 2200 Mwt showed that, in a single case, it would be necessary -to make a minor administrative change to a Technical Specifica"ion (Figure 2.1-1). Figure 2.1-1 has been.

adjusted downward the necessary a=cunt (approximately 1.5'F) to compensate for the correction. A proposed Technical Specification amendment will be submitted to the NRC to request a formal change correcting Figure 2.1-1.

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