ML20135D220
| ML20135D220 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/03/1985 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20135D222 | List: |
| References | |
| NUDOCS 8509130412 | |
| Download: ML20135D220 (29) | |
Text
___- -
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A UNITED STATES
{
g NUCLEAR REGULATORY COMMISSION L
j WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO' FACILITY OPERATING LICENSE Amendment No.41 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated May 21, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is reasonabl'e assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this 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 been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, are hereby incorporated into the license.
8509130412 050903 DR ADOCK O 37 y
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I The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A Technical Specification Changes I
Date of Issuance: September 3, 1985 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 41 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Repisce the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Amended Page 2-1 2-3 3/4 1-21 3/4 1-23 3/4 2-19 3/4 3-2 3/4 3-15 3/4 3-16 3/4 3 3/4 3-18 3/4 3-19 3/4 3-20 3/4 3-21 4
i
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL. POWER, pressurizer pressure, and the highest operating loop coolant temperature (T,yg) shall not exceed the limits shown in Figure 2.1-1.
APPLICABILITY:
MODES 1 and 2.
ACTION:
Whenever the point defined by the combination of the highest operating loop average tempereture and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.
APPLICABILITY:
MODES 1, 2, 3, 4 and 5.
ACTION:
MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
MODES 3, 4 and 5 i
Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.
P
[
i SEQUOYAH - UNIT 1 2-1 Amendment No.
41
r~
This page deleted.
e SEQUOYAH - UNIT 1 2-3 Amendment No. 41
o REACTIVITY CONTROL SYSTEMS CONTROL R00 INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figure 3.1-1.
l APPLICABILITY:
MODES 1* and 2*#.
ACTION:
With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:
a.
Restore the control banks to within the limits within two hours, or b.
Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or c.
Be in HOT STANDBY'within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
W5ee Special Test Exceptions 3.10.2 and 3.10.3.
- With K,ff greater than or equal to 1.0.
SEQUOYAH - UNIT 1 3/4 1-21 Amendment No. 41
F This page deyeteg, G
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i SEQUOYAH - UNIT I 3/4 1 23 Amendment No. 41
TABLE 3.2-1
~
M j
DN8 PARAMETERS x
LIMITS C5 4 Loops In PARAMETER Operation w
< 583*F Pressurizer Pressure
> 2220 psia
- Limit not applicable during either a THERMAL POWER ramp in excess of 5% RATED THERMAL POWER w) per minute or a THERMAL POWER step in excess of 10% RATED THERMAL POWER, physics test, or performance of surveillance requirement 4.1.1.3.b.
m h
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5:
o TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 8.<
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4
s 1.
1 2
1, 2, and
- 1 2.
Power Range, Neutron Flux 4
2 3
1, 2 2
3.
Power Range, Neutron Flux 4
2 3
1, 2 2
High Positive Rate 4.
Power Range, Neutron Flux, 4
2 3
1, 2 2
High Negative Rate R
5.
Intermediate Range, Neutron Flux 2
1 2
1, 2, and
- 3 T
6.
Source Range, Neutron Flux A.
Startup 2
1 2
2
, and
- 4 B.
Shutdown 2
0 1
3, 4 and 5 5
7.
Overtemperature Delta T Four Loop Operation 4
2 3
1, 2 6,
I 8.
Overpower Delta T Four Loop Operation 4
2 3
1, 2 6,
9.
Pressurizer Pressure-Low 4
2 3
1, 2 6
10.
Pressurizer Pressure--High 4
2 3
1, 2 6
s 11.
Pressurizer Water Level--High 3
2 2
1, 2 7
f E
TABLE 3.3-3 h
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8
Y Z
MINIMUM t
TOTAL NO.
CHANNELS CHANNELS APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Q
1.
SAFETY INJECTION, TURBINE TRIP AND g
FEEDWATER ISOLATION a.
Manual Initiation 2
1 2
1,2,3,4 20 b.
Automatic Actuation 2
1 2
1,2,3,4 15 Logic 1
c.
Centainment 3
2 2
1,2,3 16*
Pressure-High k**
d.
Pressurizer 3
2 2
1, 2, 3#
16*
i' Pressure - Low U
e.
Differential 1, 2, 3 Pressure Between Steam Lines - High Four Loops 3/ steam line 2/ steam line 2/ steam line 16*
~
Operating any steam line f.
Steam Flow in Two 1, 2, 3 Steam Lines-High Four Loops 2/ steam line 1/ steam line 1/ steam line 16*
{
Operating any 2 steam a
lines a
F i
8
o TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8
5*
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
~
COINCIDENT WITH EITHER T,yg--Low-Low 1, 2, 3,,
Four Loops 1 T,yg/ loop 2 T,yg 1 T,ygany 16*
any Operating loops 3 loops OR, COINCIDENT WITH Steam Line Pressure-Low 1, 2, 3 Four Loops 1 pressure /
2 pressures 1 pressure 16*
w)
Operating loop any loops any 3 loops w
2.
a.
Manual 2
1 2
1,2,3,4 20 b.
Automatic Actuation 2
1 2
1,2,3,4 15 Logic c.
Containment Pressure--
4 2
3 1,2,3 18 High-High 3.
CONTAINMENT ISOLATION a.
Phase "A" Isolation k
1)
Manual 2
1 2
1,2,3,4 20 2)
From Safety Injection 2
1 2
1,2,3,4 15 Automatic Actuation z
Logic W
l l
=
1 TABLE 3.3-3 (Continued) vs JS ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8
5*
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE si FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4
b.
Phase "B" Isolation g
1)
Manual 2
1 2
1,2,3,4 20 2)
Automatic 2
1 2
1,2,3,4 15 Actuation Logic
~
3)
Containment 4
2 3
1,2,3 18 Pressure-High-High c.
Containment Ventilation R8 Isolation a.
Y 1)
Manual 2
1 2
1,2,3,4 19 0
2)
Automatic Isolation 2
1 2
1,2,3,4 15 Logic 3)
Containment Gas 2
1 1
1,2,3,4 19 Monitor Radioactivity-High
-~
4)
Containment Purge 2
1 1
1,2,3,4 19 Air Exhaust Monitor Radioactivity-High
.5)
Containment Particu-2 1
1 1,2,3,4 19 g
late Activity High o
t:e 2
P JP h
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION a
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i
U i
e 4.
STEAM LINE ISOLATION I
f a.
Manual 1/ steam line 1/ steam line 1/ operating 1,2,3 25 i
steam line f
b.
Automatic 2
1 2
1,2,3 23 i
Actuation Logic c.
Containment Pressure--
4 2
3 1,2,3 18 High-High 4
d.
Steam Flow in Two 1, 2, 3 Steam Lines--High Y
I$
Four Loops 2/ steam line 1/ steam line 1/ steam line 16*
Operating any 2 steam i
lines COINCIDENT WITH EITHER i
T
--Low-Low 1, 2, 3
- 9 Four Loops 1T
/ loop 2T any 1T any 16*
- 9 loof 9 3108%E Operating OR, COINCIDENT WITH Steam Line Pressure-1,2,3 Low Four Loops 1 pressure /
2 pressures 1 pressure 16*
s g
Operating loop any loops any 3 loops a
E
?
o 1
.s
TABLE 3.3-3 (Continued)
~
b ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8s*
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION p
5.
2 FEEDWATER ISOLATION a.
. Steam Generator 3/ioop' any oper-each oper-2/ loop in 2/ loop in 1, 2, 3 16*
Water Level--
High-High
.ating, loop ating loop 6.
Manual Initiation 2
1 2
1,2,3 24 s*
b.
Automatic Actuation 2
1 2
1,2,3 23 Y
Logic U
c.
Mai, t!a. Gen. Water Levst *T9-Low i.
s Motor Driven Pumps 3/sta. gen.
2/sta. gen.
2/stm. gen.
1,2,3 16*
any sta gen.
11.
Start Turbine-Driven Pump 3/ste gen.
2/sta. gen.
2/sta. gen.
1,2,3 16*
any 2 stm. gen.
g' d.
S.I.
Start Motor-Driven ~
3 g-Pumps and Turbine "l
Driven Pump See 1 above (all S.I. initiating functions and requirements)
~
~
~
TABLE 3.3-3 (Centinu:d)
~
X; jE ENGINEEREO SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SE E
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE c:
25 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
-1 F"
e.
Station Blackout Start Motor-Driven Pump associated 2/ shutdown 1/ shutdown 2/ shutdown with the shutdown board board board 1, 2, 3 20 board and Turbine Driven Pump f.
Trip of Main Feedwater Pumps R*
Start Motor-Driven Pumps and Turbine i'
Driven Pump 1/ pump 1/ pump 1/ pump 1, 2 20*
g.
Auxiliary Feedwater Suction Pressure-Low 3/ pump 2/ pump 2/ pump 1,2,3 20*
- 7.
LOSS OF POWER a.
6.9 kv Shutdown Board
--Loss of Voltage 1.
Start Diesel 2/ shutdown 1 loss of 2/ shutdown 1, 2, 3, 4 20*
jf Generators board voltage on board g
any shutdown gf.
board 2.
Load Shedding 2/ shutdown 1/ shutdown 2/ shutdown 1, 2, 3, 4 20*
y[
board board board
- NOTE:
This technical specification is to be implemented during the startup following the 2nd refueling outage or following completion of the modification, whichever is earlier.
i H
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t
TABLE 3.3-3 (Continued) fh ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g
s 2
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE Si FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION A
b.
6.9 kv Shutdown Board g,
Degraded Voltage 1.
Voltage Sensors 3/ shutdown 2'/ shutdown 2/ shutdown 1, 2, 3, 4 20*
board board board 2.
Diesel Generator 2/ shutdown 1/shu'tdown 1/ shutdown 1, 2, 3, 4 20*
Start and Load board board board Shedding Timer t*
3.
SI/ Degraded 2/ shutdown 1/ shutdown 1/ shutdown 1, 2, 3, 4 20*
Voltage Enable board board board y
Timer U
e e
a cesgk UNITED STATES y,
g NUCLEAR REGULATORY COMMISSION y
WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating license No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated May 21, 1985, complies with the standards and requirements of-the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission;
~
C.
There is reasonabl'e assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 2.C.(2) of Facility Operating license No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 33, are hereby incorporated into the license.
.=_-;-
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. The licensee shall operate the facility in accordance with the Technical Specifications.
s 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance:
September 3, 1985 O
ATTACHMENT TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 t
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
i Amended fage 2-1 4
2-3 3/4 1-21 3/4 1-23 i
-3/4 2-17 3/4 3-2 1
3/4 3-15 3/4 3-16 3/4 3-18.
j 3/4 3-19 7
k l
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^
4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant temperature (T**9) shall not exceed the limits shown in Figure 2.1-1.
APPLICABILITY:
MODES 1 and 2.
ACTION:
Whenever the. point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig.
APPLICABILITY: MODES 1, 2, 3, 4 and 5.
ACTION:
MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
MODES 3, 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.
J i
i SEQUOYAH - 2 2-1 Amendment No. 33
i This page deleted.
SEQUOYAH - 2 2-3 Amendment No. 33
REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shal1~be limited in physical insertfor, as shown in Figure 3.1-1.
APPLICABILITY:
Modes 1* and 2*#.
ACTION:
With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:
Restore the control banks to within the limits within two hours, or a.
b.
Reduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or c.
Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- See Special Test Exceptions 3.10.2 and 3.10.3.
- With K,77 greater than or equal to 1.0.
SEQUOYAH - UNIT 2 3/4 1-21 Amendment No.
33 i
~
This page deleted.
SEQUOYAll - UNIT 2 3/4 1-23 Amendment No. 33
TABLE 3.2-1 1?
ll DNB PARAMETERS x
c
[{
LIMITS
~
4 Loops In PARAMETER Operation Reactor Coolant System T,,9
< 583*F Pressurizer Pressure
> 2220 psia
- ti i
Y
.F E.
M a
E
- Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL u,
POWER per minute or a TiiERMAL POWER step in excess of 10% of RATED THERMAL POWER, physics test, or performance of surveillance requirement 4.1.1.3.b.
l
TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION O$
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE
[
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
=
U 1.
1 2
1, 2, and
- 1 2.
Power Range, Neutron Flux 4
2 3
1, 2 2
3.
Power Range, Neutron Flux 4
2 3
1, 2 2
High Positive Rate 4.
Power Range, Neutron Flux, 4
2 3
1, 2 2
High Negative Rate
{
5.
Intermediate Range, Neutron Flux 2
1 2
1, 2, and
- 3 Y
6.
Source Range, Neutron Flux A.
Startup 2
1 2
2
, and
- 4 B.
Shutdown 2
0 1
3, 4 and 5 5
7.
Overtemperature AT Four Loop Operation 4
2 3
1, 2 6,
8.
Overpower AT Four Loop Operation 4
2 3
1, 2 6,
N 9.
Pressurizer Pressure-Low 4
2 3
1, 2 6#
E 10.
Pressurizer Pressure--High 4
2 3
1, 2 6#
[
11.
Pressurizer Water Level--High 3
2 2
1, 2 7#
U
TABLE 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 8
5x MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE E
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 4
m 1.
SAFETY INJECTION, TURBINE TRIP AND FEEDWATER ISOLATION a.
Manual Initiation 2
1 2
1,2,3,4 20 b.
Automatic Actuation 2
1 2
1,2,3,4 15
~ ~ -
Logic c.
Containment 3
2 2
1, 2, 3,
16*
Pressure-High
,s*
d.
Pressurizer 3
2 2
1, 2, 3#
16*
{
Pressure - Low on e.
Differential 1,2,3 Pressure Between Steam Lines - High Four Loops 3/ steam line 2/ steam line 2/ steam line 16*
Operating any steam line 3
t a
?
TABLE 3.3-3 (Crntinued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION u,
m f!
MINIMUM g!
TOTAL NO.
CHANNELS CHANNELS APPLICABLE I
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION i
Ei f.
Steam Flow in Two 1, 2, 3 tj Steam Lines-High to Four Loops 2/ steam line 1/ steam line 1/steaa line 16*
Operating any 2 steam lines COINCIDENT WITH EITHER T,,g--Low-Low 1, 2, 3 4d Four Loops 1 T,,g/ loop 2 T,,g 1 T,,g any any 16*
[]
Operating loo s 3 loops k
OR, COINCIDENT WITH Steam Line Pressure-Low 1, 2, 3 Four Loops 1 pressure /
2 pressures 1 pressure 16*
Operating loop any loops any 3 loops N
R
%e O
e
TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION u,
m f5 MINIMUM 55 TOTAL NO.
CHANNELS CHANNELS APPLICABLE 3:
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 55 c.
Containment Ventilation
- q Isolation
^2 1)
Manual 2
1 2
1,2,3,4 19 2)
Automatic Isolation 2
1 2
1,2,3,4 15 Logic 3)
Containment Gas 2
1 1
1,2,3,4 19 Monitor Radioactivity-High 4)
Containment Purge 2
1 1
1,2,3,4 19 Air Exhaust Monitor Radioactivity-High Id 5)
Containment Particu-2 1
1 1,2,3,4 19 late Activity High Y'
iii; 4.
STEAM LINE ISOLATION a.
Manual 1/ steam line 1/ steam line 1/ operating 1,2,3 25 steam line b.
Automatic 2
1 2
1,2,3 23 Actuation Logic c.
Containment Pressure--
4 2
3 1,2,3 18 High-High
@i d.
Steam Flow in Two 1, 2, 3 g
Steam Lines--High
!I Four Loops 2/ steam line 1/ steam line 1/ steam ifne 16*
A Operating any 2 steam lines
TABLE 3.3-3 (Continued) g; ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION e
o ll MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE NODES ACTION c:&
H COINCIDENT WITH EITHER T**U --Low-Low 1,2,3 na Four Loops 1 T**9/ loop 2Tl*9 31o8lE any 1T any 16*
Operating 10o OR, COINCIDENT WITH
~
Steam Line Pressure-1,2,3 Low 13 Four Loops 1 pressure /
2 pressures 1 pressure 16*
Operating loop any loops any 3 loops 4=
Y 5.
TUR8INE TRIP &
FEEDWATER ISOLATION a.
Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2, 3 16*
Water Level--
any oper-each oper-High-High ating loop ating loop N
's n
1
e
-