ML023370075

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License and Tech Spec Page for Amendment No, 213
ML023370075
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 11/25/2002
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML023370075 (14)
v • d • e


Text

C.

This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level ENO is authorized to operate the Amdt. 213 facility at steady state reactor core power 11-26-02 levels not in excess of 3067.4 megawatts thermal (100% of rated power).

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 213 are hereby incorporated in the License. ENO shall operate the facility in accordance with the Technical Specifications.

(3)

Less Than Four Loop Operation ENO shall not operate the reactor at power levels above P-7 (as defined in Section 7.2 of the Final Facility Description and Safety Analysis Report) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by ENO and approval for less than four loop operation at power levels above P-7 has been granted by the Commission and amendment of this license.

(4)

Pressurizer Weld inspection The results of the UT inspection of Amdt.16 pressurizer weld L-1 (ref. Appendix A 8-11-78 Technical Specification 4.2.5.f) shall be reported to the NRC and approval of the results obtained prior to return to power operation following the second refueling shutdown.

D.

(DELETED)

Amdt.46 2-16-83 E.

(DELETED)

Amdt.37 5-14-81 Amendment No. 213

Definitions 1.1 1.1 Definitions MODE (continued)

OPERABLE-OPERABILITY PHYSICS TESTS QUADRANT POWER TILT RATIO (QPTR)

RATED THERMAL POWER (RTP) vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a.

Described in FSAR Chapter 13, Initial Tests and operations;

b.

Authorized under the provisions of 10 CFR 50.59; or

c.

Otherwise approved by the Nuclear Regulatory Commission.

QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3067.4 MWt.

(continued)

INDIAN POINT 3 I

Amendment 213 1.1 -

5

SLs 2.0 This curve does not provide allowable limits for normal operation.

(see LCO 3.4.1, Pressure, Temperature and Flow DNB limits, for DNB limits) 680 660 640 LL IJ..

M M

1=

I.

1'.

L_

0 0

rM a'

c-0 10 20 30 40 50 60 70 80 90 Rated Power (Percent of 3067.4 MWt) 100 110 120 Figure 2.1-1 Rated Power (Percent of 3067.4 MWt) 100 PERCENT RATED POWER IS EQUIVALENT TO 3067.4 MWt Pressures and temperatures do not include allowance for instrument error INDIAN POINT 3 2.0-2 Amendment 213

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 6)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

1.

Safety Injection

a.

Manual Initiation 1,2,3.4 2

B SR 3.3.2.6 NA

b.

Automatic 1.2,3.4 2 trains C

SR 3.3.2.2 NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

c.

Containment 1.2.3 3

D SR 3.3.2.1 s 4.80 psig Pressure-Hi SR 3.3.2.4 SR 3.3.2.7

d.

Pressurizer 1.2,3 (b) 3 D

SR 3.3.2.1 k 1690 psig Pressure-Low SR 3.3.2.4 SR 3.3.2.7

e.

High Differential 1.2,3 3 per D

SR 3.3.2.1 NA Pressure Between steam SR 3.3.2.4 Steam Lines line SR 3.3.2.7

f.

High Steam Flow in 1, 2 (d).3(d) 2 per D

SR 3.3.2.1 (c)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with 1.2 (d), 3 (d)

I per D

SR 3.3.2.1

  • 538 *F T.,-

Low loop SR 3.3.2.4 SR 3.3.2.7 (continued)

(a)

Not used (b) Above the Pressurizer Pressure interlock.

(c) Less than or equal to turbine first stage pressure corresponding to 54% full steam flow below 20% load, and increasing linearly from 54% full steam flow at 20% load to 120% full steam flow at 100% load, and corresponding to 120% full steam flow above 100% load.

Time delay for SI n 6 seconds.

(d)

Except when all MSIVs are closed.

Amendment 213 INDIAN POINT 3 3.3.2-8

ESFAS Instpumentation 3.3.2 Table 3.3.2-1 (page 2 of 6)

Engineered Safety Feature Actuation System Instrurmentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

1. Safety Injection (continued)
g.

High Steam Flow in 1,2 (d), 3 (d) 2 per D

SR 3.3.2.1 (c)

Two Steam Lines steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with 1.2 (d).

3 (d) 1 per D

SR 3.3.2.1 2 500 Steam Line steam SR 3.3.2.4 psig Pressure-Low line SR 3.3.2.7

2.

Containment Spray

a.

Manual Initiation 1.2.3.4 2 per B

SR 3.3.2.6 NA

train, 2 trains
b.

Automatic 1.2.3.4 2 trains C

SR 3.3.2.2 NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

c.

Containment 1.2.3 2 sets E

SR 3.3.2.1

  • 24 psig Pressure (Hi-Hi) of 3 SR 3.3.2.4 SR 3.3.2.7 (continued)

(c) Less than or equal to turbine first stage pressure corresponding to 54% full steam flow below 20% load, and increasing linearly from 54% full steam flow at 20% load to 120% full steam flow at 100% load, and corresponding to 120% full steam flow above 100% load.

Time delay for SI : 6 seconds.

(d) Except when all MSIVs are closed.

INDIAN POINT 3 Amendment 213 3.3.2-9

ESFAS InstrAJmentati on 3.3.2 Table 3.3.2-1 (page 4 of 6)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

4. Steam Line Isolation
a. Manual Initiation 1.2 (d),

3 (d) 2 per F

SR 3.3.2.6 NA steam line

b. Automatic Actuation 1. 2 (d), 3 (d) 2 trains G

SR 3.3.2.2 NA Logic and Actuation SR 3.3.2.3 Relays SR 3.3.2.5

c. Containment Pressure 1.2 (d),

2 sets of E

SR 3.3.2.1

& 24 (Hi-Hi) 3(d) 3 SR 3.3.2.4 psig SR 3.3.2.7

d. High Steam Flow in 1, 2 (d).

2 per D

SR 3.3.2.1 (c)

Two Steam Lines 3 (d) steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with T.,-

1.2 (d).

1 per D

SR 3.3.2.1

= 538'F Low 3 (d) loop SR 3.3.2.4 SR 3.3.2.7

e. High Steam Flow in 1,2 (d).

2 per D

SR 3.3.2.1 (c)

Two Steam Lines 3 (d) steam SR 3.3.2.4 line SR 3.3.2.7 Coincident with Steam 1.2 (d).

I per D

SR 3.3.2.1

(c) Less than or equal to turbine first stage pressure corresponding to 54% full steam flow below 20% load, and increasing linearly from 54% full steam flow at 20% load to 120% full steam flow at 100% load, and corresponding to 120% full steam flow above 100% load.

Time delay for SI ý 6 seconds.

(d)

Except when all MSIVs are closed.

Amendment '213 3.3.2-11 INDIAN POINT 3

1-F 1.1 1

'-4 03

'-4 CA) tC,,

C.)

C.)

100 f t I

I I

I I

,..Heatup Rate 40 OF/hr I

I T

1

r RTNDT Initial:

74 Deg F I

RTNDT After 16.17 EFPY: 1/ T = 214 Deg F Heatup Rate ST 172 De F 20F/hr 150

-to i-.

(D (D

-).

0 AC.

(0.

o o-J C/i-200 250 Tcol d (Degrees F) 300 350 2500 2000 -

//~

Material Property Basis Controlling Material:

Plate Metal Copper Content:

0.240 wt. %

SIeuRte=HtpRt Phosporous Content: 0.012 wt. %

=

i Heatup Rate Heatup Rate 60 OF/hr 40 *F/hrI Curves are applicable for heatup rates to 60 OF/hour for the service period up to 16.17 EFPY, and contain the following Instrument error margins:

Temoerature; 30'F Pressure.

43 psi for 0 <P < 1500 psIg, using PT-413, 433, 443 108 psi for 1500C < P< 1700 psig, using PT-402,403 30 psi for 1700 < P5 2500 psig, using PT-455,458,457,474 Curves Include allowance for differential pressure effects due to RCP and RHR pump operation.

C.

U)

W CL E

8 0

1500 1000

-4. -

4 500 L

L I ;...

0 400 t

I A

I I

I I

t r

I r

I

=

1 I

I

(,/.

"T* t

W LA)

S.

3* >

f l4I4 4.

434 4

4-

34 4

3 3 3 3?

4, I I. j.

I.*..

3 S4.. 4 444 4

4.34,

  • 4 14 44 34 33 t4..

4.""

4 3. 3. -

:I:: ::;

c-p

.4.3 I t +.

3

="i4

  • l

.3.1 1 4.4

.4 0

0

-n to I-"

1./C C+

r'1 (rD

-3 0

C+

to

~CA cCA)

Co 0,,

-J U'

100 150 250 T cold (Degrees F) 300 350 2500 1

3.

ij.

,,i I

+/-

Material Pronerty Basis Cooldow.

Controlling Material:

Plate Metal Rate CopperContent:

0.240 wt. %

Deg

.osporous Content: 0.012 wt. %

0 RTNDT Initial:

74 Deg F i~

r'

.00 2000-0 C.

  • 1500 CO T

ca 0~1000 0

0 co 500 Curves are applicable for cooldown rates to 100 lF/hour for the service period up to 16.17 EFPY, end contain the following Instrument error margins:

Temperature: 30F r

43 psi for 0 < P5_ 1500 pslg. using PT-413 433, 443 108 psi for 1500 <P <_ 1700 psig, using PT-402,403 30 psi for 1700 < P _2500 pslg, using PT-455,458,457,474 Curves Include allowance for dIfferential pressure effects due to RCP and RHR pump operation.

0 C-)

(A

-I CA) -'.

.. J.

CA) (/4 400 S;.i I : ; ' ',

i I

I t

i I

I 200

Curves are applicable for heatup rates to 60,F/hour for the service period up to 16.17 EFPY. and contain the, following Instrument error margins:

Temoerature: 30*F Pressure:

43 psi for 0 < P < 1500 psig, using PT-413, 433, 443 108 psi for 1500 < P 5 1700 psig, using PT-402,403 30 psi for 1700 < P5 2500 psig, using PT-455,456,457,474 Curves Include allowance for differential pressure effects due to RCP and RM-IR pump operation.

Cn (A

r+

03 (A

C-)

C+

9 I

Co I

a a

I 3

a a

.a=

I19 89psig @

348.0*F a 1 a

a O.;,..., :

..a.

3 a

-t I.

I a

I 2485.0 gslg Q

@367 F 3...

.___LII.I a

a a

© a

a Material Propertv Basis Controlling Material:

Plate Metal Copper Content:

0.240 wt. %

SHeatup Rate Phosporous Content: 0.012 wt. %

Heatup Rate 60 IF/hr

.. !.+.

[+

40 *F/hr.

100 150 200 250 Tcold (Degrees F) 300 350 400

no 2000 2000O RTNDT Initial:

74 Deg F RTNDT After 16.17 EFPY: 1AT - 214 DegF H

Rate 3

T172DegF He a tupRate sA T=

17 Deg 20 OF/hr (0

CO CL W.,

1500 1000

-

a 500 0

1 "70 C-)

-4 I-"

S--J.

I I

Z m

I ý'ý I

I i

I I

t I

.o

LTOP 3.4.12

  • i"~~

~

...o

-4 I

~4.

I 3I I.

t....

~~~

~...

".'..."*'.-'t":"

10 T "..........

Cc, Cc>

..-- :-.-- Ji

-8.-

C,10

-'-'rT TTT

= -'" TT~

~ 1

... -.:-.-;-'r'1 Ir -

CD V... to in V 4

-8"or-t (919d) ejflssGJd SOIU Figure 3.4.12-1:

Maximum Allowable Nominal P.RV Setpoint for LTOP (OPS)-

1617 EFPY INDIAN POINT 3 Amendmnent*212) 3.4.12-9

80 CA)

CA)

-I

-A.

C+a M

r*

N*

M

.0-a

-a

-$1 acn 0

200 TcOLD (OF) 250 300 350 Figure applicable to 16.17 EFPY Curves represent maximum allowable pressurizer level for the conditions defined.

RCSPressure(PSIG)

Less Than 400 I.:

t.

/

I Curves'includ( the followin' instrument.'un ertainty:

"Temperature:

.O.F Pressure,: 43 isi "Pressurizer 1.vel uncertan

',y: 7%.

/

/I I

.. '.300 350..

70 60 150 ci, N

W~

50 40 30 100 20 10 0

so M'D

C) 0i La4 0

(D CA Ct

(,A, 03.0 to.

0. -3 (D

CA 061 -.

ON

'CD*

-3...

0*

400 Figure applicable to 16.17 EFPY Curves represent maximum allowable pressurizer level for the conditions defined.

so 40 Curves irlude the'following inst-uBnent under ainty:.

"Temperature: 30'F Pressure: 43 psi-4 Pressurizer level unc rtainty: :7%

"S RCSPressure(PSIG).

' i "

~Less Than 1O00; 5500 t,

i I

06

,+-,Z" CA)

'-a l-.a 350

,,J N

C,,

C,,

30 20 10 0

50 C-,.

'-a La

100 150

.200 250 Tr 0o (OF) 300 C

LTOP 3.4.12 0 C 0

L E

I-r Figure 3.4.12-4: Secondary Side Limitations for RCP Start With Secondary Side Hotter than Primary Side, 16.17 EFPY Amendment 213 3.4.12-12 INDIAN POINT 3

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Applicable Neutron Flux Trip Setpoint in Percent of RATED THERMAL POWER MINIMUM NUMBER OF MSSVs APPLICABLE Neutron Flux Trip Setpoint PER STEAM GENERATOR

(% RTP)

REQUIRED OPERABLE 4

  • 60 3
  • 41 2
  • 22 Amendment 213 INDIAN POINT 3 3.7.1-3
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