ML20077F114

Proposed TS Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements Change

ML20077F114
Person / Time
Site:	Millstone
Issue date:	12/02/1994
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20077F113	List: B15039, Application for Amend to License NPF-49,revising TS Table 4.3-1 by Adding Note for Functional Unit 2b Re Reactor Trip Sys Instrumentation Surveillance Requirements Change ML20077F114
References
NUDOCS 9412130271
Download: ML20077F114 (6)

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l Docket No. 50-423 l

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l Attachment 1 Millstone Unit No. 3 Proposed Revinion to Technical Specifications Reactor Trip System Instrumentation Surveillance Requirements Change Marked-Up Pages December 1994 941213o271 941202 PDR ADOCK 050C 0423 P ppq

IABLE 4.3-1

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REACTOR TRIP SYSTEM INSTRUENTATION SURVEILLANCE REOUIREMDITS J :';-

. 4, m TRIP 3

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. : ANALOG ACTWTIM IRIDES FOR CHANNEL DEVICE WHICN

' CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTURTION SURVEILURE E FWCTIONAL WIT CHECK CALIBRATION TEST IEST LOGIC.TESI

[ 1. Nansal Reactor Trip N.A. N.A.

IS MOUIRE N.A. R(14,20) N.A. 1,2,3*,4*L .:

5* u I

2. Power Range, Neutron Flux l a. High Setpoint S D(2,4), Q N.A. R.A. 1, 2 ,,

i M(3,4),

Q(4,6),  !

R(4,5,20)

b. Low Setpoint S R(4, S/U(1) N.A. M.A. 1***,2 i

\

w 1 3. Power Range, Neutron Flux, M.A. R(4. 20) Q N.A. N.I. 1, 2

. High Positive Rate L 5g o 4. Power Range, Neutron Flux. N.A. Q N.A. N.A. 1, 2 High Negative Rate R(4(20)g

5. Intermediate Range ,

S R(4.5) S/U(1) N.A. M.A. 1***, 2

6. Source Range Neutron Flux S R(4. 5) S/tf(l), N.A. N.A. 2**, 3, 4, Q(9) 5 g 7. Overtemperature AT $ R Q N.A. N.A. 1, 2 p

h. 8. Cla w ;. AT S R Q N.A. N.A. 1, 2 2

g.

f E

.o Pressertzer Pressure--Low S R(20) Q(18) N.A. N.A. 1

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10.' Pressurizer Pressure--Nigh 5 R(20) Q(18) N.A. R.A. 1, 2 D' w-1

11. Itessurizer Uater. level--Nigh- 5 R(20) Q.. . N.A. .N.A. 1 r 12 teacter Coolant Flow--Low 5 R(20' 4 N.A. N.A. k

' . 12/22I92

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TABLE 4.3-1 (Continued)'

TABLE NOTATIONS

• When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

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

• • • 8elow P-10 (Low setpoint Power Range Neutron Flux Interlock) Setpoint. .

• • • • Above the P-9 (Reactor Trip / Turbine Interlock) Setpoint.

(1) If not performed in previous 31 days.

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

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above i

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.

s euw e Ru+f ,

(5) Detector plateau curves shall b obtained, and evaluated and compared to manufacturer's data. For the Flux channels the provisions'(intermediate of Specification 4.0.4 Range areand notPower Range Neutron applicable for entry into MODE 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)

I (9) Quarterly surveillance 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 annunciator window. ,

t STONE - UNIT 3 3/4 -13 Amendment No pp, 70

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Docket No. 50-423 I

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I Attachment 2 Millstone Unit No. 3 Proposed Revision to Technical Specifications Reactor Trip System Instrumentation Surveillance Requirements Change Retyped Pages 1

l December 1994

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0;: TABLE 4.3-1 -

0; y REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

• TRIP ANALOG ACTUATING MODES FOR E CHANNEL DEVICE WHICH q CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS RE0UIRED

1. Manual Reactor Trip N.A. N.A. N.A. R(14,20) N.A.

g 2, 3*, 4*,

2. Power Range, Neutron Flux

a. High Setpoint S Di;2,41 , Q N.A. N.A. 1, 2 Mi,3,4? ,

, ,'20)

b. Low Setpoint S R(4, 5, 20) S/U(1) N.A. N.A. 1***, 2 w 3. Power Range, Neutron Flux, N.A. R(4, 5, 20) Q N.A. N.A. 1, 2

) High Positive Rate Y 4. Power Range, Neutron Flux, N.A. R(4,5,20) Q N.A. N.A. 1, 2 g High Negative Rate

5. Intermediate Range S R(4,5) S/U(1) N.A. N.A. 1***, 2

6. Source Range, Neutron Flux S R(4,5) 1), N.A. N.A.

g**,3,4, g 7. Overtemperature AT S R Q N.A. N.A. 1, 2 R 8. Overpower AT S R Q N.A. N.A. 1, 2 E

g 9. Pressurizer Pressure--Low S R (20) Q(18) N.A. N.A. 1 g

10. Pressurizer Pressure--High S R (20) Q(18) N.A. N.A. 1, 2 g 11. Pressurizer Water Level--High S R (20) Q N.A. N.A. 1

( 12. Reactor Coolant Flow--Low S R (20) Q N.A. N.A. I

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3 TABLE 4.3-1 (Continued)

TABLE NOTATIONS

• When the Reactor Trip System breakers are closed and the Control Rod Drive System .is capable of rod withdrawal.

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

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

i

• • • • Above the P-9 (Reactor Trip / Turbine hurlock) Setpoint.

( l (1) If not performed in previous 31 days. j (2) Comparison of calorimetric to excore power indication above 15% of RATED 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. j (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 l uot applicable for entry into MODE 2 or 1. j (4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

1 (5) Detector plateau curves shall be obtained, and evaluated and compared to I manufacturer's data. For the Source Range, Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not l applicable for entry into MODE 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) l (9) Quarterly surveillance in MODES 3*, 4*, and 5* shall also include l verification that permissives P-6 and P-10 are in their required state 1 for existing plant conditions by observation of the permissive annunciator window.

NIgLSTONE-UNIT 3 3/4 3-13 Amendment No. pp 79,