ML18227A424

Submit Licensee Event Report of Turkey Point Unit 4, in Accordance with Technical Specification 6.9.2 to Provide Prompt Notification, Occurrence on 4/18/1977 for Nominal Power

ML18227A424
Person / Time
Site:	Turkey Point
Issue date:	05/02/1977
From:	Schmidt A Florida Power & Light Co
To:	Moseley N Office of Nuclear Reactor Regulation
References
PRN-LI-77-130
Download: ML18227A424 (8)

Text

U.S. NUCLEAR REGULATORY CO ION OQCggENUMBER~

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NRC FoRM I2 76) ~

FILE NUMBER

. NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL INCIDENT REPORT TO: FROM: DATE OF DOCUMENT Florida Power & Light Company 5/2/77 Mr. Norman CD Moseley Miami, Florida DATE RECEIVED A~ D, Schmidt 5/27/77 0 NOTOR I2E 0 PROP INPUT FORM NUMBER OF COPIES RECEIVED ETTE R SfoR IG INAL QCOP Y fgUNC I.ASS IF I E D g/6'6 DESCRIPTION ENCLOSURE Licensee Event Report (RO 50-251/77-3) .on 4/18/77 concerning discussions with their vendor showing that Tech Spec Fig 2 '-1,

".Reactor Core Thermal & HydraUlic Safety Limits", requires revisioni ~ ~ ~ ~ ~

PLANT NAME:

Tuikey Point Unit No.,4 (1-P) (2-P)

RJL NOTE ~ IF PERSONNEL EXPOSURE 1S INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTION LIC~ ASST~ ppvrS W CYS ACRS CYS Z NG S NT INTERNAL DISTRIBUTION G FIL HRC PDR ICE (2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SIIAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION C NTROL NUMBER LPDR:

TIC NRC FORM 196 {2.76)

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FLORIDA POWER & LIGHT COMPANY May 2, 1977 PRN-LI-77-130

$ p+Rblff Mr. Norman C. Moseley, Director, Region II WAYSV~977 Office of Inspection and Enforcement Q.~k 14INEAR RKGULATO><

COhNI SS lOII U. S. Nuclear Regulatory Commission IMI ~l A 230 Peachtree Street, N. W., Suite 1217 Atlanta, Georgia 30303

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 251-77-3 TURKEY POINT UNIT 4 DATE OF OCCURRENCE: APRIL 18, 1977 NOMINAL POWER 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. Schmidt

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Vice President Power Resources MAS/cpc Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (40)

Director, Office of Management Information and Program Control (3) 7714701g9 PEOPLE... SERVING PEOPLE

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LICENSEE EVENT REPORT COiVTROL BLOCK: , (PL~ E PAINT AU. AEQUIAEO INFOAMATION7 UCENSEc UCENSE EVENT NAMc LICENSE NUMBEA TYPc 01 F T P S 4 0 0 0 0 0 0 0 0 0 d 1 1 1 1 ~01 TYPc

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7 89 14 15 25 26 30 31 32 AGPOAT AEPQAT C'TEGQAY OQCKKT NUMBEA ~ EVENT OATE REPORT OATE

~01 CGN'T 0 5 0 0 2 5 0 4 1 8 7 7 4 2 9 7 7 7 6 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION

~02 is sions with our NSSS vendor have shown that Technical S ecification Fi ure 2.1-1 as 80

[OD~] "Reactor Core Thermal and H draulic Safet Limits" re uires revision. .An analvsis 7 8 9 80 tOD4] performed at 2200 Mwt has ielded a corrected Fi ure 2.1-1 a licable to both Units 3 a9 80 Qg and 4. No chan es to set 'pints o eratin limits or o eratin ractices are re uired 7 8 9 80 QO 6 as a result of this correction. Neither unit has ever o crated nonconservativel as a 7 8 9 PILe I c 80 7

tao>J 8 9 10 SYSTEM COOK

~zI z CAUSE CQOE

~p 11 12 z

COMPONENT COOK z z z z Z 17 Z,

COMPONENT SUFFUKA 43 44 Z

CCMFONKNT MApi4rACAJFKA 9 9 9 47 VCLAnON N

48 CAUSE OESCRIPTION 7 6 9 Tisourewcauedbv a difference betw en t e values of "nominal ower" a lied I 80 7

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89 v i is and 4 bv FPL a d the NSSS vendor. The vendor erforms anal ses 60

'~IIC wer of 2200 Mwt our icensed stead state reactor core thermal 7 89 FACIUTY MEiHQO OF POWcR

'5 STATUS ~ III OTHER STATUS OISCOVEAY OISCOVERY OESCAIPTIQN 7 6 9

~E ~iO 10 O

12 13 NA 45 NSSS Vendor Discussions FOAM QF 80 ACTIVITY COATKNT AP~SEO OF RK'&SE AMOUNT QF ACTIVITY LOCATION OF AELEASc HI 7 8 9 lzJ hJ 10 11 NA 44 45 NA PERSONNEL EXPOSURES NUMBGEA TYPc OESCA~iN fg]89~oo o 11

~z 12 13 80 PERSONNEL IN JUR'S NUMBEA CESCAIPTION 7

~ilc 89

~00 0 11 12 NA P+QQ~LE CONSEQUENCES 7 8 9 80 LOSS OR OAMAGE TO FACIUTV TYPc OKSCA,'PTI N

~z NA 7 89 10 PUSL:CITV NA 7 89 AOOITIONAL FACTORS

[116] See Pa e Tso for continuation. of Event Descri cion and Cause Description 7,8 9 80 89 80 NAME M. A. Scho man PHONE. 305/552-3802

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REPORTABLE OCCURRENCE 251-77-3 LICENSEE EVENT REPORT PAGE 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 4 involving a nonconservative specification on reactor core thermal and hydraulic safety limits. A similar report (250-77-5) will be submitted for Unit 3.

(251-77-3)

Cause Descri tion (continued) power output. However, they recently advised us that the specific number being used for analytical work was 2192 Hwt. 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 Specification (Figure 2.1-1). Figure 2.1-1 has been adjusted downward the necessary amount (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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