ML20059C239
| ML20059C239 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/23/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059C244 | List: |
| References | |
| NUDOCS 9008310129 | |
| Download: ML20059C239 (11) | |
Text
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g UNITED STATES E'
f, NUCLEAR REGULATORY COMMISSION y
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WAsHWoToN,0. C. 7066s k...*
e ILLINOIS POWER COMPANY ET AL.,
E0,CKET NO. 50-461 0
C_LINTON POWER STATION. UNIT NO. 1
+
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.44 Liranse No. NPF-61.
1.
The Nuclear Regulatory Commission (the Commission) has fochd that:
A.
The application for amendment by Illinois Power Company" (1 6.
and Soyland Power Cooperative, Inc. (the licensees) dated February 5, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulatit,ns set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Couission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and s.ety of the public, and (ii) that such activities will be conducted r
in compliance with the Commission'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 witn 10 CFR Fart $1 of the Commission's regulations and all applicable requirements have
- 1 been satisfied.
2.
Accordingly, 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-62 is hereby amended to read as follows:
- 1111nois Power Company is authorized to act as e. gent for Soyland Pwer Cooperative, Inc. and has exclusive responsibility and control over the physical unstruction, operation and maintenance of the facility.
9008310129 900G23 PDR ADOCK 05000461 p
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i i
t 2-i (2) Technical Specifications and Environmental Protect on Esen The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.44
, are hereby incorporated into this license.
Illinois Power Company shall oper6te the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effactive as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION gL,, -... --
e John N. Hannon, Director Project Directorate 111-3 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 23, 1990 l
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i ATTACHMENT TO LICEllSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 3-13 3/4 3-13 3/4 3-18 3/4 3-18 3/4 3-27 3/4 3-27 3/4 3-32 3/4 3-32 i
6 e
TABLE 3.3.2-1
- 2
~
5 CRVICS INSTRUNENTATION E
MINIMUM OPERABLE APPLICABLE l
ISOLATION CHANNELS PER TRIP OPERATIONAL g
q TRIP FUNCTION SIGNAL tt SYSTEM CONDITION ACTION
~
1.
PRIMARY AND SECONDARY CONTAINNENT ISOLATION l
2 *)
1, 2, 3 20 I
a.
Reactor Vessel Water Level-Low Low, B(b)(f) 25 Level 2 2 *)
1, ', 3 29 I
b.
Reactor Vessel Water Level-Low B
Low, Level 2 (ECCS Div. I and II) 2 ")
2, 3 29 I
c.
Reactor Vessel Water Level-tow B
Low, Level 2 (ECCS Div. III) 2 ")
1, 2, 3 20 I
d.
Drywell Pressure - High L(b)(f) 2 *)
1, 2, 3 29 I
A e.
Drywell Pressure - High L
(ECCS Div. I and II) w 2 *)
1, 2, 3 29 I
U f.
Drywell Pressure - High (ECCS L
l Div. III) 2 *)
5 I
l g.
Containment Building fuel Transfer Z(b)(f)
Pool Ventilation Plenum Radiation - High h.
Containment Building Exhaust Radiation - High 2 *)
1, 2, 3 29 I
ID)II)
- 1) Containment Bldg. HVAC (VR) and M
25 Drywell Purge (VQ)
E
- 2) Containment Monitoring (CM) and M
1(k) 1, 2, 3 29 Process Sampling (PS) 25
,=
I2 *)
1, 2, 3 29 i.
Containment Buf1 ding Continuous 5(b)(f) 5 Containment Purge (CCP) Exhaust 25 g
Radiation - High I) h j.
Reactor Vessel Water Level-Low U
2 1, 2, 3 '
29 25 Low Low, Level 1 0 )II) 1, 2, 3 29 k.
Containment Pressure-High P
1 25
?.
p TABLE 3.3.2-1 (Continued)
~zg CRVICS INSTRUNENTATION z
c6 MINIMUM OPERABLE APPLICABLE ISOLATION CHANNELS PER TRIP OPERATIONAL
[
TRIP FUNCTION SIGNAL t1 SYSTEM CONDITION ACTION 1.
Main Steam Line Radiation - High.
C 2(a) 1, 2, 3 23 2 *)
I Fuel Building Exhaust (b)(f)(j) m.
1, 2, 3 25 Radiation - High 25 n.
Manual Initiation R(b)(f) 1 1,2,3 26 i
25 APPLICABLE ISOLATION APPLICA8LE OPERATIONAL 2.
MAIN STEAM LINE ISOLATION t SIGNAL TABLE NOTES CONDITIONS ACTION w
a.
Reactor Vessel Water Level-Low 0
Low Low, Level 1 U
NA 1,2,3 20 b.
Main Steam Line Radiation - High C
d 1, 2, 3 23 c.
Main Steam Line Pressure - Low H
MA 1
23 i;
d.
Main Steam Line Flow - High D
NA 1, 2, 3 23 e.
Condenser Vacuum - Low J
NA 1, 2**, 3**
23 f.
Main Steam Line Tunnel Temp.
- High E
NA 1, 2, 3 23 g.
N in Steam Line Tunnel a Temp.
- High F
NA 1,2,3 23 h.
Main Steam Line Turbine Bldg.
Temp. - High G
p 1, 2, 3 23 l
i.
Manual Initiation R
NA 1,2,3 22 E
2 P.
F Un s
b e
,4 w~-
' ' ' ~ ' - * " - " ' " " - - ~ " " - ~ ^ " -
- - - ^ ^
~ " " '
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1 L
TABLE 3.3.2-1 (Continued)
CRVICS INSTRUMENTATION TABLE NOTATIONS When handling irradiated fuel in the primary or secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
N When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
When any turbine stop valve is greater than 95% open or the reactor mode switch is in the run position.
t Main steam line isolation trip functions have 2-out-of-4 isolation logic except for the main steam line flow - high trip function which has 2-cut-of-4. isolation logic for each main steam line, it See Specification 3.6.4 Table 3.6.4-1 for valves which are actuated by these isolatiot, signals.
(a) A channel may be placed ir, an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped con-dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b) Also actuates the standby gas treatment system.
(c) Deleted (d) Also trips and isolates the mechanical vacuum pumps.
(e) Isolates RWCU valves 1G33-F001 and 1G33-F004 only.
(f) Also actuates secondary containment ventilation isolation dampers per Table 3.6.6.2-1.
(g) Manual Switch closes RWCU system inboard isolation valves F001, F028, F053, F040 and outboard isolation valves F004, F039, F034 and F054.
(h) Vacuum breaker isolation valves require RCIC system steam supply pressure low coincident with drywell pressure high for isolation of vacuum breaker isolation valves.
(i) A single manual isolation switch isolates outboard steam supply line isolation valve (F064) and the RCIC pump suction from suppression pool valve (F031) only following a manual or automatic (Reactor Vessel Water Level 2) RCIC system initiation.
(j) Only actuates secondary containment ventilation isolation dampers per Table 3.6.6.2-1.
Note it is not applicable to this Trip Function.
(k) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the trip con-dition provided that the redundant trip system is OPERABLE and monitoring that parameter.
(1) Not required to be OPERABLE when valves IVR002A,B and IVQOO6A,B are sealed closed in accordance with Specification 3.6.4.
(p) Each channel consists of five temperature modules and their associated sensors.
A channel is OPERABLE if and only if five temperature modules and their associated sensors are OPERABLE.
CLINTON - UNIT 1 3/4 3-18 Amendment No.25,44
i II I
I I
TABLE 3.3.2-1 (Continued) n C5 CRVICS INSTRUE NTATION E
[
MINIMUM OPERA 8tE APPLICASLE ISOLATION CHANNELS PER TRIP OPERATIONAL l
TRIP FUNCTION SIGNAL tt-SYSTEN CONDITION ACTION 5.
RNR SYSTEM ISOLATION l
a.
IDIR Heat Exchanger A, 8 Ik) l Ambient Temperature - High T
1/rmm 1, 2, 3 28 l
b.
RNR Heat Exchanger A, 8 Cg)
ATemp. - High 5
1/ room 1, 2, 3 28 c.
Reactor Vessel Water g2,)
1,2,3 28
.1 Level - Low, Level 3 A
t Y
d.
Low Low Low, Level 1 U
2(k) 1,2,3 28 g
e.
Reactor Wessel (HHR Cut-in I2 ")
1, 2, 3 28 Permissive) Pressere - High X
f.
Drywell Pressure - High III
- 1) RHR Test Lines L
2 1, 2, 3 28 2 *)
1, 2, 3 28 I
- 2) Fuel Pool Cooling L
g.
Manual Ini'~
son R
1 1,2,3 26 3
,g O
l j
TABLE 4.3.2.1-1 n
C I
- RVICS INSTRUE NTATION SURVEILLANCE REQUIREMENTS E
c.
CHANNEL OPERATIONAL 5
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVFILLANCE REQUIRED 1.
PRIMARY AND SECONDARY CONTAIMENT ISOLATION i
a.
Low Low, Level 2 S
M R(b) 1, 2, 3, #
b.
Low Low, Level 2 (ECCS Div. I and II)
S M
R(b) 1, 2, 3 c.
m i
}
Low Low, Level 2 (ECCS r
Div. III)
S M
R(b) 1, 2, 3 i
i m
d.
Drywell Pressure - High S
M R(b) 1, 2, 3 e.
Drywell Pressure - High (ECCS Div. I and II)
S M
R(b) 1, 2, 3 I
f.
Drywell Pressure - High (ECCS Div. III)
S M
R(b) 1, 2, 3 g.
Containment Suilding Fuel Transfer Pool Ventilation Plenum Radiation - High 5
M R
N l
h.
Contairment. Building Exhaust Radiation - High g
- 1) Containment Building HVAC 2
g (VR) and Drywell Purge (VQ)
S M
R 1, 2, 3, #
- 2) Containment Monitoring (CM) and Process Sampling (PS)
S M
R 1, 2, 3, #
e 3
[
i.
Containment Building Contin-g uous Containment Purge (CCP) Exhaust Radiaticn -
High 5
M R
1,2,3,#
k
TABLE 4.3.2.1-1 (Continued) c> -
C CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS
'i E
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH c-TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 5
[
1.
PRIMARY AND SECONDARY CONTAINMENT ISOLATION (Continued) j.
Reactor Vessel Water Level-Low Low Low, Level 1 S
M R(b) 1, 2, 3, #
k.
Containment Pressure - High 5
M R
1,2,3,#
l 1.
Main Steam Line Radiation -
High S
M R
1,2,3 m.
Fuel Building Exhaust Radiation - High 5
M R
1,2,3,#
n.
Manual Initiation NA R
MA 1, 2, 3, #
g i
w 2.
MAINSTEAELINEISOLATION o$
a.
Low Low Low, Level 1 5
M R(b) 1, 2, 3 ji i
b.
Main Steam Line Radiation -
High S
M R
1, 2, 3 c.
Main Steam Line Pressure -
Low 5
M R(b) y d.
Main Steam Line Flow - High S
M R(b) 1, 2, 3 e.
Condenser Vacuum - Low S
M R(b) 1, 2**, 3**
f.
Main Steam Line Tunnel Temp. - High 5
M R
1, 2, 3
~
g.
Main Steam Line Tunnel I
A Temp. - High 5
M R
1,2,3 h.
Main Steam Line Turbine Bldg.
Temp. - High S
M R
1,2-3 i.
Manual Initiation MA R
MA 1,2,3
~
e
+
e
.+
r.
2 4
..-.+-, _ -,
m.
,_4,
.-y.o--___
m m mm.
TABLE 4.3.2.1-1 (Continued) n
{
CRVICS INSTRUNENTATION SURVEILLANCE REQUIRENENTS Ax CHANNEL' OPERATIONAL c-CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED S.
RHR SYSTEN ISOLATION a.
RHR Heat Exchanger Rooms A, 8 Ambient Temp. - High S
M R
1, 2, 3 b.
RHR Heat Exchanger Rooms A, 8 A Temp. - High 5
M-R 1,2,3 c.
Low, Level 3 5
M R(b) 1 2, 3 d.
R Low Low Low, Level 1 5
M R(b) 1, 2, 3 w
e.
Reactor Vessel (RHR Cut-in g
Permissive) Pressure - High S
M R(b) 1,2,3 f.
Drywell Pressure - High
- 1) RHR Test Line S
M R
1,2,3
- 2) Fuel Pool Cooling S
M R
1, 2, 3 g.
Manual Initiation MA R
NA 1,2,3 1
0 TABLE 4.3.2.1-1 (Continued)
CRVICS INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS
- When handling irradiated fuel in either the secondary or the primary containment and during CORE ALTERATICNS and operations with a potential for draining the reactor vessel,
- When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operatiot.; with a potential for draining the reactor vessel.
- With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10,1 or 3.9.10.2.
- When any turbine stop valve is greater than 95% open or the reactor mode switch is in the run position.
(a) Each train or logic channel shall be tested at least every other 31 days.
(b) Calibrate the analog trip modules at least once per 31 days.
CLINTON - UNIT 1 3/4 3-32 Amendment No. 44 l
l