ML18227B248
| 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
NRC FoRM 195
,(2~78)
/
8'0/0 U.S. NUCLEAR REGULATORY COM NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL
-zoo zg j F
E NUMBE TO:
Mr. Victor Stello FROM:
Florida Power
& Light Company Miami, Fla, Robert ED Uhrig DATE OF Dg))M)NT DATE RECEIVED 6/27/77 ETTE R RIG INAI QCOP Y DESCRIPTION 0 NOTOR I2E D
)REIN C LASS IF I E D PROP INPUT FORM EN CLOSU RE NUMBER OF COPIES RECEIVED j S/gM~
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, ~ ~ ~ ~
ZCKNOVrMDGVD
-PL'ANT NAME:
Turkey Point Units 3 8
'RJL 6/29/77 (1-P)
(4-p)
FOR ACTION/INFORMATION ENVIRHNMENTAL ECT MANAGER:
ICENSING ASSISTANT:
.A.Va
~ 5 ASSIGNED AD:
V~ MOORE LTR BRANCH CHIEF:
PROJECT MANAGER:
LICENSING ASSISTANT:
Bo HARLESS INTERNALDISTRIBUTION STFMS SAFETY HEINEMAN ROEDER PLANT SYSTEMS TEDESCO BENAROYA SITE SAFETY &
ENVIRON ANALYSIS DENTON & MULLER ENGINEERING IPPOLITO OPERATING REACTORS ENVIRO TECH ERNST BALLARD GBLOOD VA ZT8CZY CHECK AT&I ALTZMAN TBERG EXTERNALDISTRIBUTION BAER BUTLER GRIME GA1&IILL 2
SITE ANALYSIS VOLLMER BUNCH Ji COLLINS KREGER CONTROL NUMBER TIC REG IV J
HANCHETT 16 CYS ACRS SENT CAT GO NRC FORM 195 I2.76)
NSIC 77iSOOOyy,
II
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P. O. BOX OI3100, MIAMI,FLORIDA 3310I 8
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+II//g FLORIDA POWER 8t LIGHT COMPANY June 23, 1977 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 S 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.
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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650 640 2400 PSXA 630 l-l CD I
620 2250 PSZA 2100
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C$
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dJ CA S
Ol')
610 600 1900 PSZA 590 580:
1700 PSEA 570 20 60 80 106 Rate" Pcher (Percent)
'l20 r:.=
-= '.1-.]. ~ctar om Th rmaf and Hydrauti Sa ey Li Three 4'pe~t~
4~
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FLORIOA PO'/lEA 5 LIGHTCOMPANY May 2, 1977 PRN-LI-77-131 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement 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)
PEOPI.E... SERVING PEOPLE
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LICENSEE EVENT REPQRT CCNTFICL eLCCV:
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eO et EVeluT OESCFIIPTION
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ja'o Technical S ecification Pi ure 2.l-l 7
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~CI3 "Reactor Core dermal and H draulic Safet Limits" reauizes revision.
An analysis 7
99
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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
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d the HSSS vendor.
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np 4c eo m'owez of 22 0 Nwt. ou licensed steadv sLate reactor core ther.al
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a 9 kDGITIONA'A TCre See Pa e
T-o for co"..=== ". ='Qn a Event Description and Cause Description.
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FHgNS. 305/552-3802
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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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