ML18227C697

Letter Request to Amend Appendix a of Facility Operating Licenses

ML18227C697
Person / Time
Site:	Turkey Point
Issue date:	01/31/1975
From:	Robert E. Uhrig Florida Power & Light Co
To:	Anthony Giambusso Office of Nuclear Reactor Regulation
References
Download: ML18227C697 (22)

Text

t NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)

CONTROL NO:

FILE'O:

oo a

ower L g 0 Co Miami, Pla.

33101 Mr.,R.E. Uhrig A. Giambusso DATE OF DOC 1-31-75 ORIG 3 signed CC OTHER SENT AEC PDR SENT LOCALPDR DATE REC'D LTR TWX RPT OTHER 2~5~75 CLASS UNCLASS PROPINFO XXX INPUT NO CYS REC'D 40 QQ NO:

50-25 51 DESCRIPTION:

Ltr requesting'n amdt to the OL....notarized 1-31-75....trans the following.....

PLANT NAME:

turkey Point 3

& 4 ENCLOSURES:

Proposed change to the tech specs

~ ~ ~ ~ ~ ~ ~ ~

concerning....consistency between the protective instrumentation setpoints and remainder of the instrumentation setpoints...

(40 cys encl rec'd)

FOR ACTION/INFORMATION 2-5-75 JB BUTLER (L)

W/ Copies CLARK (L)

W/ Copies PARR (L)

W/ Copies KNIEL (L)

W/ Copies SCHWENCER (L)

W/ Copies STOLZ (L)

W/ Copies VASSALLO (L)

W/ Copies PURPLE (L)

W/ Copies ZIEMANN(L)

REGAN (E)

W/ Copies W/ Copies DICKER (E) v LEAR (L)

W/ Copies WQCopies KNIGHTON (E)

SPELS W/ Copies W/ Copies YOUNGBLOOD (E)

W/ Copies W/ Copies INTERNALDISTRIBUTION o REG FILE R~

V OGC, ROOM P-506A V'OSSI CK/STAFF CASE GIAMBUSSO BOYD MOORE (L)

DEYOUNG (L)

SKOVHOLT (L) v.GOLLER (L) (Ltr)

P. COLLINS DENISE

~REG OPR FILE 5 REGION (2)

T.R. WILSON STEELE TECH REVIEW SCHROEDER MACCARY KNIGHT PAWLICKI SHAO STELLO HOUSTON NOVAK ROSS IPPOLITO TEDESCO LONG LAINAS BENAROYA VOLLMER DENTON GR IMES R.

GAMMI LL H.

KASTNER E.

BALLARD P;

SPAN G LE R J.

M.

ENVIRO S.

MULLER M.

DICKER S.

KNIGHTON M.

YOUNGBLOOD H..

REGAN S.

m PROJECT LDR G.

~C'~~a,~

V.

HAR LESS

~ R.

LIC ASST DIGGS (L)

GEAR IN (L)

GOULBOURNE (L)

KREUTZER (E)

LEE (L)

MAIGRET (L)

REED (F)

SERVICE (L)

SHEPPARD (L)

SLATER (E)

SMITH (L)

TEETS (L)

WI LLIAMS(E)

WILSON (L)

INGRAM (L)

A/T IND.

BRAITMAN SALTZMAN MELTZ PLANS MCDONALD CHAPMAN

~ DUBE (Ltr) y'. COUPE PETERSON HARTFIELD (2)

KLECKER EISENHUT WIGG I NTON EXTERNAL DISTRIBUTION W1 LOCAL P DRANmi~~4 W1 TIC (ABERNATHY)

(1)(2)(10) NATIONALLABS

~1 NSIC (BUCHANAN) 1 W. PENNINGTON', Rm E-201 GT 1 ASLB 1

CONSULTANTS 1 Newton Anderson NEWMARK/BLUME/AGBABIAN

< I 9, ACRS HOLDING/SENT 1 PDR-SAN/LA/NY~

1 BROOKHAVEN NAT LAB 1 G. U LR I KSON, 0 R N L 1 AGMED (RUTH GUSSMAN)

Rm B-127 GT 1 J. D. RUNKLES, Rm E-201 GT

r lC dsf" i ht

"'r g~f 1

+t"

<aI I

~

~

~

~

~

~

~

~ w 3'9~"

I ff 1 l "k+

>"< )

3 i

> ~

~

~

o '1~<1'"f gag-4 =)<.,g-)c

~

r ~,>

)~

~ g s)y 'rgj

~per'i>

e

~

~,~e

~

q> 9$ 'tg

)

) ','fy I

)+j g 'rg$ f

~ t),W,',,

f)g" fI'g,<'I

'~ 'yt) ~

~ ~

~ ~ ~f l a+

g g)Q g

=-t ~

4'lf($

w 7 8y 4

'I fjjgl'

.ie )

.,)

f

• ]All'r

P. 0 013100, AtIIAMI,FLORIDA 33101

+All/g

=o

=

FLORIDA POWER 5 LIGHT COMPANY January 31, 1975 L-75-54 Mr. Angelo Giambusso, Director Division of Reactor Licensing Office of Nuclear Reactor Regulation U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Giambusso:

Re:

Turkey Point Unit Nos.

3 and 4

Docket Nos.

0-250 and 50-251 Proposed Amen to Facility 0 eratin Li:censePs DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power

& Light Company submits herewith three

{3) signed originals and forty {40) conformed copies of a request to amend Appendix A of the Facility Operating Licenses DPR-31 and DPR-41.

We can avoid abnormal occurrence reports which have no safety significance and establish consistency between the protective instrumentation setpoints and the remainder of the instrumentation setpoints by utilizing the allowances for setpoint tolerance contained in the safety analyses.

Florida Power 6 Light Company and the Nuclear Steam Supply System vendor have investigated the protective instrumentation Technical Specifications in conjunction with the safety analyses provided in the FSAR and established proposed Technical Specifications which incorporate an instrument setpoint tolerance.

The proposed changes are as set forth in the attached revised Technical Specification pages bearing the date of 1/17/75 in the lower right hand corner and as described below.

~2. 3-2 Under the heading "Specification" change 25% to 26%.

2~2.3-2 Add a factor of 1.035 to the coefficient of LTD contained in the expression for the overtemperature sT setpoint at the top of the page.

J g$g~g HELPING BUILD FLORIDA

~ y t

n

Mr. Angelo Giambusso January 31, 1975 2~2. 3-3 Add a factor of 1.03 to the coeffi'cient of ATD contained in the expression for the overpower sT setpoint. at the top of the page.

Under the heading of Pre's'suri'zer in the middle of the page, change-2 1715 psig to 1680 psig 2385 psig to 2375 psig 92% to 93%

Under the heading of Reactor'oo'lant Fl'ow change 90% to 89% and 56.1 Hz to 56.0 Hz.

Pa

e. '2'.'3'- 4 Tn paragraph 1. 0,

change 1 0% to 11% and in paragraph 2. 0,

change 45% to'6%,

Tab'le 33.'5'-4 In the column headed Setpoint,'hange 1715 psig to 1680 psig and 5% span to 4% span.

/cry y yours, Robert E. Uhrig Vice Pxesident REU:HNP:nch Attachments cc:

Mr. Norman C. Moseley Mr. Jack R.

Newman

1 (5

U t'

l, C

II

STATE OF FLORXDA

)

)

COUNTY OF DADE

)

SS ROBERT E.

UHRIG, being first duly sworn, deposes and says:

That he 'is a Vice Pres'ident of Florida Power 6 Light Company, the Licensee hex'ein; That he has executed the foregoing instrument, that the statements made 'in this said instrument're 'rue 'and correct to the 'best of his knowledge, infoxmation and belief; and that he is authorized to execute the instrumen't of said Licensee.

o ert rag Subscribed and sworn to before me this I

>o g

7 1975.

o ary u

.zc, xn an

"= ",', of 'Floxida at Large Ny>,Commission expires'x t e tate hlOTARY PUSLIC, State of Fin<i"+ st i Rr'fe My Commission Expnes August 24, 1975 SOndedbyAUTOOYINSRS INSQRANCb

p

~ ~

2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION qv

~Ob ective:

Applies to trip settings for instruments monitoring reactor power; reactor coolant pressure, temperature and flow; pressurizer level; and steam generator level.

eie V To prev'ent the principal process variables from exceeding a safety limit.

Reactor trip settings shall be as follows:

Nuclear Flux Power range (low set point) equal to or less than 26%

of rated power, may be bypassed when power is greater than 10% of rated power.

Power range (high set point) equal to or less than 109% of rated power.

2.3 -1 1/17/75

~ ~

Reactor Coolant Tem erature Overtempera-ture AT.

1. 035 0 ~ 0174(T 566 6) + 0 ~ 000976 (P 1885) f(Aq)

AT Indicated hT at rated power, F

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 t

b where q

and q

are the percent power in the top and bottom halves of the core respectively, and q

+ q is total c'ore.power. in percent of rated t

power, f(Aq) = 0.

Fbr each percent. that the magnitude of (q - q )

exceeds

+10 percent, the Delta-T trip, set point shall be automatically reduced by 3.5 percent of its value at interim power.

For each percent that the magnitude of (q q )

exceeds

-14 percent, the Delta-T trip set point shall be automatically reduced by 2 percent of.

its value at interim power.

Kl (Three Loop Operation)

= 1.120; (Two Loop Operation)

= 0.88 2'-2 1/17/75

~ I P

I I

Over-power DT

<AT 1.03 1 09 K K (T - T') f (Aq) 1 dt, 2

AT 'ndicated AT at rated power, F

0 T

Average temperature, F

K2 Indicated average temperature at nominal conditions and rated power, F

0 for decreasing average temperature, 0.2 sec./F for increasing average temperature 0.00134 for T equal to or more than T';

0 for T less than T'ate of change of temperature F/sec dT dt f(Aq) -

As defined above Pressurizer Low Pressurizer pressure equal to or greater than 1680 psig.

High Pressurizer pressure equal to or less than 2375 psigo High Pressurizer water level equal to or less than 93% of full scale.

Reactor Coolant Flow Low reactor coolant flow equal to or greater than

,89% of normal indicated flow Low reactor coolant pump motor frequency equal to or greater than 56.0 Hz Under voltage on reactor coolant pump motor bus equal to or greater than 60% of normal voltage Steam Generators Low-low steam generator water level equal to or greater than 5% of narrow range instrument scale 203-3 1/17/75

II'

Reactor Tri Interlocks Protective instrumentation settings for reactor trip interlocks shall be as follows:

l.

Above 11% of rated power, the low pressurizer pressure trip, high p'ressurizer level trip and the low reactor coolant flow trip (for two or more loops) are made functional.

2 ~

Above 46% of rated power the, single loop loss of flow trip is made functional. It need not be made functional below 60% of rated power for two loop operation, if the overtemperature hT trip setpoint has been adjusted using K

~ 0.88.

1

2. 3-4 1/17/75

4 TABLE 3.5-4 ENGINEERED SAFETY FEATURE SET POINTS NO ~

FUNCTIONAL UNIT CHANNEL ACTION SET POINT

'igh Containment Pressure Safety Injection Containment Spray

• Steam Line Isolation

• Containment Isolation

~

6 psig 2 ~

3 ~

4 ~

5 ~

High-High Containment'Pressure Pressurizer (coincident)

Low Pressure Low Level High Steam Line Differential Pressure (2/3 between any header and any line)

. High Steam Line Flow (2/3 lines)

Coincident with:

Low Steam Line Pressure, Or Low Tavg.

See No.

1 Safety In5ection H

Safety Injection Safety In)ection Steam Line Isolation

< 30 psig

> 1680 psig

> 4%'pan

< 150 psi d/p for 3.84 10 6 lb/hr, 770 psig, 100%

RP d/p for 0.64'10 6 lb/hr, 1005 psig, 0%

RP d/p linear with 1st stg.

press'

0-100%

RP

> 600 psig

> 531 F

• High and High-High coincident 1/17/75

0

SAFETY EVALUATION The revised instrument limiting safety system settings are con-sistent with the stated bases for such setpoints and represent the most current approach to such setpoints.

The target value for the setpoints used for actually setting the device will remain unchanged".

The change is a change on, paper (Technical Specifications) to properly make allowance for the practical limitations that exist in actually achieving a given setpoint.

The limiting setpoint values as established in Chapter 14 of the FSAR have not been altered.

The allowance for instrument error still exists between the revised Technical Specification and the=-

safety analyses values as stated in the Technical Specification Bases.

The attached Table provides a comparison of the revised Technical Specifications and the limiting setpoint values utilized in the safety analyses provided in Chapter 14.0. of the FSAR.

• In the case of the pressurizer high pressure trip setpoint, the target value for the actual setpoint device will be revised but it will be revised in the conservative direction to correspond to the requested change in the Technical Specification which is also in the conservative direction.

~

r ~

COMPARISON OF THE LIMITING SETPOINT ASSUMED IN THE SAFETY ANALYSES AND THE PROPOSED TECHNICAL SPECIFICATIONS (LSSS)

'nstrument Channel Proposed Technical S ecification Margin for Instrument Error (1)

Limiting Value Assumed in the Safety Analyses (2)

Nuclear Flux Tri (Low range, hxgh level)

Nuclear Flux Permissive Interlocks P-7 P-8 Pressurizer Pressure Tri s Low Pressure (1900 psia operation)

High Pressure (1900 psia t

operation)

Pressurizer Hi h Level Tri

<26%

<11%

<46%

>1680 psig

<2375 psig

<93%

8%

8%

20 psi 10 psi 34%

19%

54%

1660 psig 2385 psig 100%

Low Loop Flow Low Frequency, Pump Power

'Supply Pressurizer Low Level (SI)

Overpower hT (1900 psia)

>89%

>56. 0 Hz

>4%

<1. 03

( >Tp Coefficient) 3 Hz

=4%

87 53 Hz 0%

l. 07 (hT~

Coefficient)

(SEE TECHNICAL SPECIFI CATION~

PAGE NO ~

2 3

3 FOR DEFINITION OF COEFFICIENT)

Overtem erature hT, (1900 sia) 3-Loop Operation 2-Loop Operation

<1.035

(,hT Coefficient)

<1.035 (hT Coefficient) 0

-"6%

=8%

l. 09 (LTo Coefficient) 1.11 (aT Coefficient)

OTES:

1.

The allowed margin is always greater than, or equal to the overall channel accuracy.

2.

These values were provided by the NSSS vendor and were derived from the safety analyses provided in Chapter 14.0 of the Turkey Point Unit Nos.

3 and 4 FSAR.

I 0

I 0