Text

Amend 13 to License NPF-76,changes Tech Specs by Modifying Calibr Requirements for source-range Neutron Monitor Circuitry to Allow for Installation of New Model Low Noise Preamplifier
	ML20034A032
Person / Time
Site:	South Texas
Issue date:	04/03/1990
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20034A033	List: ML20034A032; ML20034A038;
References
	NUDOCS 9004190203
	Download: ML20034A032 (7)
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UNITED STATES Ig' NUCLEAR REGULATORY COMMISSION n

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WASHINGTON, D. C. 20555

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HOUSTON LIGHTING & POWER COMPANY, CITY PUBLIC SERVICE-BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET N0.,,50-498-SOUTH TEXAS PROJECT UNIT 1 AMENDM,E,NT,TOFACILITVOPEMLIM_ LICENSE a

Amendment No.13 License No. NPF j 1.

The Nuclear Regulatory Comission (the Comission) has found that:

1 A.

The application for amendment by Houston Lighting & Power Company * (HL&P) acting on behalf of'itself and for the City' PublicServiceBoardofSanAntonio(CPS),CentralPowerand

~ Light Company (CPL). and City of Austin, Texas (C0A)- (the.

~

licensees) dated ~ January 25, 1989, complies;with the standards q'

and requirements of-the' Atomic Energy Act of 1954, as amended (the Act), and the' Commission's rules and regulations set forth in 10.CFR i

Chapter'.I; B.

The-facility will operate in conformity with the. application, as amended, the provisions of the Act, and the rules and regulations-l of the Comission; C.

There is reasonable assurance:

(1)thattheactivitiesauthorized

~

by this amendment can be conducted without endcngering,the health I

and' safety-of the public, and-(ii) that such activities.will be-conducted in compliance with the' Comission's regulations; ~

-1 D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements: have -

l been satisfied.

9004190203 900403 PDR ADOCK 03000498

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P PDC

' Houston DghlTEg & Power Company is authorized to act for the City Public i

Service Board of' San Antonio, Central Power and Light Company and City of H

Austin, Texas and has exclusive responsibility and control over:the physical

'l construction, operation and maintenance of the facility.

t unus

' 2.

Accordi.ngly, the license is' amended by changes' to the Technical Specifi--

cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-76.is hereby amended to read as follows:

4 2.

Technical ~ Spec _ifications 1

The Technical Specifications contained in Appendix A,'as revised-through Amendment No.13, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The. licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective 30 days from the date of-issuance.

FOR THE NUCLEAR REGULATORY COMMISSION-bikAO./JJA Frederick J. H<

don, Director Project Directorate IV-Division of Reactor Projects - III, IV, V and Special Projects- -

4 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 3,1990 1

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ATTACHMENT T0_ LICENSE AMENDMENT N0.,,,13 FACILITY ~0PERATING LICENSE NO. NPF-76 DOCKET NO. 50-498 Replace the following pages of the Appendix' A Technical Specifications with-the attached pages. The revised pages-are identified by Amendment number and contain verticaltlines indicating the areas of change. The corresponding overleaf pages are also provided to maintain; document completeness.-

Remove Insert 3/4 3-11 3/4 3-11, 3/4 3-14 3/4 3-14 i

l i

I

-l y

l i

v, TABLE 4.3-1 o

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS' w

-TRIP 3;

ANALOG ACTUATING MODES FOR CHANNEL

-DEVICE WHICH c

CHANNEL' CHANNEL OPERATIONAL OPERATIONAL = ACTUATION SURVEILLANCE.

g FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST

' LOGIC TEST 15 REQUIRED 1.

Manual Reactor Trip N.A.

N.A.

R(14)

N.A.

1, 2, 3*,

4*, 5*

2.

Power' Range, Neutron Flux m

a.

High Setpoint S

0(2, 4),

Q(17)-

N.A.

1, 2 -

M(3, 4),

Q(4, 6),

R(4, 5) l b.

Low Setpoint S

R(4)

S/U(1)

N.A.

1***,

2^

3.

Power Range, Neutron N.A.

R(4)

Q(17)

N.A.

1, 2 y

Flux, O

High Positive Rate 4.

Power Range, Neutron N.A.

R(4)

Q(17)-

N.A.

1, 2

Flux, High Negative. Rate 5.

Intermediate Range, S

R(4,'5)

S/U(1)

N.A.

M.A.

1***, 2 l"

Neutron Flux

_c

' h 6.

' Source' Range,: Neutron. S R(4, 5)-

S/U(1),

Flux Q(9)(17)

N.A.

2**,

3, 4, 5 g

7.

Extended Range, S

R(4)

Q(12, 17)

N.A.

3,4;5 y

Neutron Flux k

8.

Overtemperature AT

.S R

'Q(17)

N.A.

1, 2

[ 9.

Overpower AT S

R Q(17)

N.A.

1, 2.

[ 10.

Pressurizer Pressure

'.o

--Low 5

R

.Q(1)

-N.A.

N.A.

I

_ _ = _ _ _ -.

=-

TABLE 4.3-1 (Continued) l y,

'8I REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS R

TRIP 3;.

ANALOG ACTUATING MODES FOR CHANNEL-DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE c

CHECK CALIBRATION TEST TEST

' LOGIC TEST-

'IS REQUIRED 3. FUNCTIONAL UNIT 11.

Pressurizer Pressure

--High S

R Q(17)

N.A.

1, 2 e.

~

12.

Pressurizer Water Level--High S

R Q(17)

N.A.

l-13.

Reactor Coolant Flow

--Low S

R-Q(17,.18)

N.A.

I 14.

Steam Generator Water wg level--Low-Low S

R Q(17,18)

N.A.

N. A.

1, 2 15.

Undervoltage - Reactor Coolant Pumps N.A.

R N.A.

Q(17)

N.A.

I

16. Underfrequency -

Reactor Coolant

. Pumps-N.A.

R N.A.

Q(17)

N.A.

1 17.

Turbine Trip a.

Low Emergency N. A.

R N.A.

S/U(1,10)

N. A. -

1 Trip Fluid Pressure b.

Turbine-Stop N.A.

R N.A.

S/U(1,10)

N. A.

1 Valve Closure

18. -Safety Injection

'N.A.

N.A.

R N.A.

1, 2 Input from ESFAS

.f

-_m s_%,._w

=r a~ - - '- - " - - ' ' ' ' - - - - ~ - - ' " ' " ~ ^

^ ~ ' '

" " ' ' ' ' ' ~ ' ~ ' ' " ^ ' ~

' - ~ ' ' " ' ' ' ~ ~ ~ ' -

'~

c TABLE 4.3-1 (Continued) m

o

.h REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIRENENTS m

TRIP 5

ANALOG ACTUATING-NDDES'FOR CHANNEL DEVICE-MfICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE E FUNCTIONAL UNIT CHECK CALIBRATION TEST

. TEST LOGIC TEST 15 REQUIRED

~"_ 19.

Reactor Trip System Interlocks

[

a.

Intermediate Range Neutron Flux, P-6 N. A.

R(4)

R-N.A.

N.A.

2**

b.

Low Power Reactor Trips Block, P-7 N.A.

R(4)

R N.A.

N.A.

1 c.

Power Range Neutron

,g Flux, P-8 N.A.

R(4)

R

.N.A.

N.A.

1 y

d.

Power Range Neutron g

Flux, P-9 N.A.

R(4)

R

_N.A.

N. A.~

.1.-

e.

Power Range Neutron Flux, P-10 N.A.

.R(4)

R N.A.

N.A.

1, 2 f.

Turbine Impulse Chamber Pressure, P-13 N.A.

R R

N.A.

M.A.

1-20.

Reactor Trip Breaker N.A.

N.A.

N. A.

M(7,11)

N.A.

1, 2, 3 *, 4 *, $*

21. Automatic Trip and Interlock N.A.

- N. A.

N.A.

M. A.

M(7) 1, 2, 3*,-4*, 5*

Logic 22 Reactor Trip Bypass. Breaker N.A.

N.A.

M(15),R(16)

N.A.

1, 2, 3*,

4*,.5*

a--

d

~

I TABLE 4.3-1 (Continued)

I TABLE NOTATIONS i

When the Reactor Trip System breakers are closed and the Control Rod Drive i

System is capable of rod withdrawal, h

- Below P-6 (Intermediate Range Neutron Flux. Interlock) Setpoint.

i

- - Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed.in previous 31 days.

(2)' Comparison of calorimetric to excore power indication above 15% of RATED.

t THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.

The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.

i (3)- Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference'is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau-curves shall be obtained and evaluated.

If a low nois'e i

preamplifier is used with the Source Range Detector, no plateau curve is obtained.

Instead,'with the high voltage tetting varied as recommended' by the manufacturer, an. initial discriminetor bias curve shall'be L

measured for each detector.

Subsequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.

For the i

Intermediate Range and Power Range Neutron Flux channels the provisions l

of Specification 4.0.4 are' not -applicable for entry into F.F 2 or 1.

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) (Not Used' (9) Quarterly mveillance in MODES 3*, 4*,'and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive l

annunciator window.

I SOUTH TEXAS - UNITS 1 & 2 3/4 3-14 Unit 1 - Amendment No. #, 13

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ML20034A032

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