ML18227C703

Letter Request to Amend Appendix a of Facility Operating Licenses

ML18227C703
Person / Time
Site:	Turkey Point
Issue date:	01/07/1977
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
Download: ML18227C703 (18)

Text

NRC FoRM 195

{2 78)

U.S. NUCLEAR REGULATORY C ISSION NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOCKET NUMBER FILE NUMBER TO: Mr Stello QfLETTER IIORIGINAL OCOPY DESCRIPTION 8 NOTOR IZE D IEUNCLASSIFIE D PROP Florida Power & Light Co Miami, Fla R E Uhrig INPUT FORM ENCLOSURE DATE OF DOCUMENT 1-7"77 DATE RECEIVED ] ] 3 77 NUMBER OF COPIES RECEIVED three signed Ltr notarized 1-7-77....trans the following:

Amdt to OL/Change to Tech Specs:

Consisting of revisions with regard to change to permit operation at original normal operating pressur of 2250 psia......

PLANT NAME. Turkey Point f13 S~

~I:CKPO~EDG@D PC KOT 3,ZjIIggg SAFETY ASSIGNED AD:

FOR ACTION/INFORMATION RO ~EO HANAOEE LXC ASST PROJECT MANAGER~

LXC ASST

~

INTERNALDISTRIBUTION REG FXL I'& E g,

OELD GOSSXCK & STAFF MXPC CASE HARLESS PROJECT IIANAGEMENT BOYD PE COLLINS HOUSTON PETERSON MELTZ HELTEMES 8KOVHOLT LPDR' NSIC:

ASLB:

ACRS CYS HQLQXHG/ E NRC FORM 1S5 {2.78)

SYSTEMS SAFETY HEINEMAN

'CHROEDER ENGXNEERING IIACARRY KNIGHT SIHWEIL PA CK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NAT LAB REG V,IE LA PDR CONSULTANTS:

T

<CA PLANT SYSTEMS TEDESCO O

XPPOLITO OPERATING REACTORS STELLO OPERATING TECH EXSENHUT J

B E

ULRXKSON OR SXTE SAFE ERNST BALLARD SPANGLER SITE TECH GAMIIILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J ~ COLLINS l

KREGER CONTROL NUMBER f

~

~

1

~

~

~

~

~

~

~

P)

P. O. BOX O'I3100, MIAMI, FL 33101 ii)'Iija'~

(r FLORIDAPOWER & LIGHTCOMPANY 4&~8"iiI4I'7 ~~ABt li'LI8

Dear Mr. Stello:

Re:

Turkey Point Unit 3 Docket No.

50-.250 Qi Prop'osed Amendment to Facilit 0 eratin License DPR-31 Office of Nuclear Reactor Regulation Attn:

Victor Stello, Jr., Director Division of Operating Reacto U.

S. Nuclear Regulatory Commissio Washington, D.

C.

20555

~~gtD 1IgIIRC JA

~ggp,R R1Go II,S.

gyiIcQ gghI g ~877 ~

In accordance with'10 CFR 50.30, Florida Power 6 Light Company hereby submits three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License DPR-31.

This proposal will~allow,Unit 3 to be operated at its original normal operating pressure of 2250 psia.

A safety evaluation supporting this pressure change has been pre-pared and is attached for your review.

The proposed change is discussed below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.

Approval of this proposed amend-ment is requested by February 18, 1977.

Pacha 1-6 The Unit 3 fuel residence time limit of Specification 1.16.1 is changed to 27,000 EFPH.

Pa es 2.3-2 and 2.3-3 The equations for Overtemperature hT and Overpower bT in Specification 2.3 are revised to support operation at 2250 psia.

The limit for low pressurizer pressure is also re-vised.

The Unit 3 DNB parameters of Specification 3.1.6 are revised to support operation at 2250 psia.

PEOPLE... SERVING'EOPLE

l

~,

sj N

,<<e w p

~I 1

To:

Re:

Victor Stello, Jr.,

NRC Turkey Point Unit 3 Proposed Amendment to Facilit 0 eratinq License DPR-31 January 7, l977 Page 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.

A safety evaluation is attached.

Very truly yours, Robert E. Uhrig Vice President REU/MAS/GDW/hlc Attachments cc:

Norman C. Moseley, Region II Robert Lowenstein, Esq.

Ja

STATE OF FLORIDA

)

)

COUNTY OF DADE

)

Robert E. Uhrig, being first duly sworn, deposes and says:

That he is a Vice President of Florida Power G Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.

Robert E. Uhrig Subscribed and sworn to before me this day of NO, RY PUBLIC, in and or T@%,>gpygtg of Dade, P FLORIDA 'A7 EAR'Qf

.;State of Flora.da MYCOMMISSION EXPIRES NEXPIRES NOV. '30 I979 IIO5DED JHRU CXNERAL INSs UNDERWRITER

.Nj, ccpn~ission expires:

qNII~

I I U

I I'

1.3.6 XNTERDI LIMITS 1.16.1 Fuel Residence Ti e LMt The ~uel resic~""e t -'= fcr Unit 4 shall I

27,000 EFPH.

be limited to 30,000 ZsPB The fuel residence time for a..-t 3 sea~

be limited to 1.16.2 Reactor Coolant P ~s Ope a-ic The r'eactor shall rot be operated

- ~th ess hhaa three reactor coolant pumps in operation.

k 1.17 LOU POWER PHYSICS TESTS Low power physics tests *re tests be>-

a nomi~~U 5X of rated power'hich measure fundamental charact Hs-.cs o.

t=e reactor coze and related instrumentation.

1-6 1/7/77

I I

~

~

UNIT NO.

3 Reactor Coolant Temperature Overtemperature AT

< bTo K - 0.0107 (T 574) + 0.000453 (P-2235) f(Qq) 4T

= Indicated AT at rated power 0

T

~ Average temperature, F

P

= Pressurizer

pressure, psig f{Aq) = a function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be. selected based on measured instrument response during startup tests such that:

For (q q ) within +10 percent and -14 percent b

where q

and q

are the percent power in the top t

and bottom halves of the core respectively,.and q

+ q is total core powe" in percent of rated power, f(b,q) = 0.

For each percent that the magnitude of (q q )

exceeds

+10 percent, the Delta-T trip set point shall be autonatically reduced by 3.5 percent of its value at interim power-For each percent that the magnitude of (q q

t exceeds

-14 percent, the Delta-T trip set point.

shall be automatically recuced by 2 percent of its value at interim power.

K (Three Loop Operation)

= 1.095 1

(Two Loop Operation)

~ 0.88 2 ~ 3 2

UNIT NO.

3 1/7/77

UNIT NO.

3 Overpower AT

< AT AT0 T

K1 K2 dT dt Indicated AT at rated power, P

Average temperature, P

Indicated average temperature at nominal cond'.tions and rated power, P

0 for decreasing average temperature, 0.2 sec./P for increasing average temperature 0.00068 for T equal to or more than T';

0 for T 1ess than T'ate of change of temperature, F/sec.

f(Aq)~ As defined above Pressurizer Low Pressurizer pressure equal to or greater than 1835 psig High Pressurizer pressure equal to or less than 2385 psig.

High Pressurizer water level equal to or less than 92% of full scale.

Reactor Coolant Flow Low reactor coolant flo - equal to or greater than 90%

of normal indicated flo~.,

Low reactor coolant pu~ motor frequency equal to or greater than 56.1 Hz.

Under voltage on reacto" coolant pump motor bus equal.

to or greater than 60% o normal vo1.tage Steam Generators Low-low steam genera-or -ater level equal o or greater than 5% of narrow ran=-

instrument scale.

203-3 UNIT NO.

3 1/7/77

MET NO. 3 The followin~ D.'i~ related, param ters 1imits shall be ~inta "e" d- "'ng po=-ar operation:

a.

Reacto Cool~t System Tavg < 578.2 'P b.

Press~>>

~er Pressure

> 2220 psia-.

c.

Reactor Coola"t Plow > 268,500 gpm.

Pith any of the a"ove par-eters exceeding its limit, restore the para~ter to within its.~

within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> o

reduce thermal power to 3.ess than 5% of rated:herM power using norma1 shutdown procedures Compliance ~ath a. and b. is demonstrated by veri ying that each of the parameters is within its 'limits at 1east once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />..

Compliance with c. is de-onstrated by verifying that the parmete" is within its 1imits after'

~

each refueling cycle.

• Limit not applicable during eithe" a

~<<.RYAL PONE'amp increase in e-cess of (5%)

RATED THER~i~ PG~:-"= per =-nute ox

a. TERNAL POWER step

~ increase jn excess of (10/)

BAT:-D Ti:~L~Z. PO'r7ER 3

tN' i

4,i a. i.

aO 1/7/77

C

~

SAFETY EVALUATION Introduction This safety evaluation supports the following proposed changes to the Unit 3 Technical Specifications:

Primary system operating pressure is increased from 2100 psia to the NSSS design pressure of 2250 psia.

This affects fuel residence time, the Overtemperature hT equation, the Overpower hT equation, the LSSS limit for low pressurizer'ressure, and the limits for certain DNB parameters.

Discussion The clad flattening time, assuming 2250 psia system pressure, is predicted to be 27,000 EFPH for the limiting region (Region 2) using the current Westinghouse evaluation model.

Therefore, at a system pressure of 2250 psia, Region 2 has a nominal Cycle 4 allowed residence time of 9,900 EFPH (Cycle 2 lifetime was 6,800 EFPH, and Cycle 1 lifetime was 10,300 EFPH).

The fuel residence time limit of Technical Specification 1.16.1 is revised accordingly.

Operation at the NSSS design pressure of 2250 psia leads to changes in Technical-Specification 2.3 (Limiting Safety System Settings).

The LSSS limit for low pressurizer pressure and the equations for Overtemperature BT and Overpower BT are revised to correspond with system operation at 2250 psia.

The proposed Unit 3 limit and equations are the same as the limit and equations being used for Unit 4, which is now operating at the NSSS design pressure of 2250 psia.

Operation at. the NSSS design pressure also =leads to changes in Technical Specification 3.1.6 (DNB Parameters).

The DNB limits for pressurizer pressure and Tav are, revised to correspond with system operation at 2250 psia; R DNB limit on reactor coolant flow is added to bring the format for the Unit. 3 DNB Parameters into conformance with the format for the Unit 4 DNB Parameters.

The proposed Unit 3 Parameters are the same as the DNB Parameters being used for Unit 4, which is now operating at 2250 psia.

George, R. A., et al "Revised Clad Flattening Model",

WCAP 8377 (Proprietary) and WCAP 8381 (Non Proprietary),

July, 1974.

~

~

~

k

Conclusions Based on these considerations, (l) the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important. to safety and does

not, reduce the margin of safety as defined in the basis for any technical specification, therefore, the change does not,involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

1 E

~

~

L