ML20076N086
| ML20076N086 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/03/1994 |
| From: | Carpenter C Office of Nuclear Reactor Regulation |
| To: | Illinois Power Co |
| Shared Package | |
| ML20076N088 | List: |
| References | |
| NPF-62-A-094 NUDOCS 9411090185 | |
| Download: ML20076N086 (15) | |
Text
.
(('7)pf[4f UNITED STATES B
NUCLEAR REGULATORY COMMISSION En " 1.,
/
WASHINGTON, D.C. 20066 4001
%, N"'.
ILLINOIS POWER COMPANY. ET At.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF,
1.
The Nuclear Regulatory Commission (the Comn.ission) has found that:
A.
The application for amendment by Illinois Power Company * (IP), and l
Soyland Power Cooperative, Inc. (the licensees) dated August 12,
- 1994, complies with the standards 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 Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable 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 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 with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have 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:
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
t 9011090185 941103 PDR ADOCK 0500 1
P
l (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the l
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 94,.are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
CLL % 0 Cynthia A. Carpenter, Acting Director Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changas-to the Technical Specifications Date of Issuance: November 3,1994 3
J b
t
i,c l
l T
ATTACHMENT TO LICENSE AMENDMENT NO. 94
{
f FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 l
l t
Replace the following pages of the Appendix "A" Technical Specifications with 3
the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding i
overleaf pages, indicated by an asterisk, are provided to maintain document completeness.
Remove Paaes Insert Paaes 3/4 3-1 3/4 3-1 l
3/4 3-12 3/4 3-12 l
3/4 3-33 3/4 3-33 i
3/4 3-34*
3/4 3-34*
i 3/4 3-51*
3/4 3-51*
i 3/4 3-52 3/4 3-52 3/4 3-57*
3/4 3-57*
i 3/4 3-58 3/4 3-58 3/4 3-97*
3/4 3-97*
3/4 3-98 3/4 3-98 3/4 4-10 3/4 4-10 a
3/4 4-11 3/4 4-11 1
I
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE
- with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
APPLICABILITY: As shown in Table 3.3.1-1.
ACTION:
a.
For all functional units of Table 3.3.1-1 other than Reactor Mode Switch Shutdown Position.
1.
With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applic2ble.
2.
With two of the four channels required for ar.y Trip Function inoperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip Function already exists. The provisions of Specification 3.0.4 are not applicable.
3.
With three of the four channels required for any Trip Function inoperable, take the ACTION required by Table 3.3.1-1.
b.
For Reactor Mode Switch Shutdown Position take the ACTION as shown in Tabl e 3.3.1-1.
SURVEILLANCE RE0VIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.
- A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance provided at least two OPERABLE channels are monitoring that parameter.
CLINTON - UNIT 1 3/4 3-1 Amendment No.7J,94
E INSTRUMENTATION CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM t
LIMITING CONDITION FOR OPERATION (Continued) 3.3.2 ACTION (Continued):
2.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system
- in the tripped condition within I hour and take the ACTION required by Table 3.3.2-1.
SURVEILLANCE RE0VIREMENTS 4.3.2.1 Each CRVICS channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in i
Table 4.3.2.1-1.
i I
4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.
4.3.2.3 The CRVICS RESPONSE TIME of each CRVICS trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one logic train tested at least once per 36 months, and one channel per trip function such that all channels are i
tested at least once every N times 18 months, where N is the total number of redundant channels in a specific CRVICS trip function.
- The trip system need not be placed in the tripped condition if this would cause the Trip function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems' have the same number of inoperable channels, place either trip system in the tripped condition.
1 l
CLINTON - UNIT 1 3/4 3-12 Amendment No.77,94 I
E INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.
APPLICABILITY: As shown in Table 3.3.3-1.
ACTION:
With an ECCS actuation instrumentation channel trip setpoint less a.
conservative than the value shown in the Allowable Value column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.
With either ADS trip system "1" or "2" inoperable, restore the c.
inoperable trip system to OPERABLE status within:
1.
7 days, provided that the HPCS and RCIC systems are OPERABLE, or 2.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, provided either the HPCS or RCIC systems are inoperable.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to s 100 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1.
4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.
4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function shown in Table 3.3.3-3 shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ECCS trip system.
CLINTON - UNIT 1 3/4 3-33 Amendment No.7J,94
TABLE 3.3.3-1 Pg EMERGENCY CORE COOLING ~ SYSTEM ACTUATION INSTRUMENTATION
=
s MINIMUM OPERABLE APPLICABLE c
CilANNELS PER TRIP OPERATIONAL-TRIP FUNCTION FUNCTION CONDITIONS ACTION-
~
A.
DIVISION I TRIP SYSTEM 1.
RHR-A (LPCI MODEl & LPCS SYSTEM a.
Reactor Vessel Water Level - Low Low Low, Level 1 2'6*"
1, 2, 3, 4*, 5*
30 b.
Drywell Pressure - High 2'63'
1, 2, 3 30 c.
Reactor Vessel Pressure-Low 4'*"
1, 2, 3
- 32 (LPCI and LPCS Injection Valve Permissive) 4*, 5*
33 d.
LPCIPump(A)StartTimeDelayjogicCard l
1, 2, 3, 4*, 5*
32 LPCS Pump Discharge Flow - Low I
1, 2, 3, 4*, 5*
40-g e.
f.
LPCI Pump (A) Discharge Flow - Low" 4
g.
Manual Initiation
~
l
I, 2, 3, 4*, 5*
- 40 l'6' 1, 2, 3, 4*, 5*
35 2.
AUTOMATIC DEPRESS *JRIZATION SYSTEM TRIP SYSTEM "1"'
ADS LOGIC "A" AND "E" a.
Reactor Vessel Water level - Low Low Low, level 1 2'*"
1, 2, 3 30 b.
Drywell Pressure - High 2 '* "
1, 2, 3.
30 c.
ADS Timer l
1, 2, 3 32 d.
Reactor Vessel Water Level - Low, level 3 (Permissive)
I
I, 2, 3 30 y
e.
LPCS Pump Discharge Pressure-High (Permissive) 2'*"
I, 2, 3 32
=h f.
LPCI Pump (A) Discharge Pressure-High (Permissive) 2 ' * "
1, 2,.3 32 a
4 g.
ADS Drywell Pressure Bypass Timer 2
1, 2, 3 32
=
h.
Manual Inhibit ADS Switch 1
1, 2, 3 35 g
1.
Manual Initiation 2
1, 2, 3 35
=
w a*
.s.
,,..-m._
m
_..,m..
t.-
TABLE 4.3.4.1-1 Py ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENT 3
z CHANNEL CHANNEL FUNCTIONAL CHANNEL g
TRIP FUNCTION CHECK TEST CALIBRATION Z
1.
S Q
R*
l g
Low Low, level 2 2.
Reactor Vessel Pressure - High S
Q R*
l
- Calibrate trip unit at least once per 92 days.
M Y
5
%E
- = =
a m"
N Y.
l
A INSTRUMENTATION END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.2 The end-of-cycle recirculation pump trip (E0C-RPT) system instrumen-tation channels shown in Table 3.3.4.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of.
Table 3.3.4.2-2 and with the END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER-is 2 to 40% of RATED THERMAL POWER.
ACTION:
a.
With an end-of-cycle recirculation pump trip function instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.
b.
With one of the four channels required for any Trip Function inoperable, operation may continue provided the inoperable channel is placed in the tripped condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The provisions of Specification 3.0.4 are not applicable.
c.
With two of the four channels required for any Trip Function inoperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip Function already exists. The provisions of Specification 3.0.4 are not applicable.
d.
With three of the four channels required for any Trip Function inoperable, reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.3.4.2.1 Each end-of-cycle recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.2-1.
4.3.4.2.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.
CLINTON - UNIT 1 3/4 3-52 Amendment No. 77,94
_ TABLE 4.3.4.2-1 P
E END-OF-CYCLE RECIRCULATION PtMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS 8
z CHANNEL E
FUNCTIONAL CHANNEL-p TRIP FUNCTION TEST CALIBRATION w
1.
Turbine Stop Valve-Closure Q
R 2.
Turbine Control alve-Fast Closure Q
R R.
Y
!G B"
> a 5I a
es &
13 -M
INSTRUMENTATION 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION II;3TRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta-tion channels shown in Table 3.3.5-1 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint column of Table 3.3.5-2.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome pressure greater than 150 psig.
ACTION:
a.
With an RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b.
With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5-1.
SURVEILLANCE RE0VIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.1-1.
4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.
l l
CLINTON - UNIT 1 3/4 3-58 Amendment NoJJ4 4 9
INSTRUMENTATION 3/4.3,9 PLANT SYSTEMS ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9 The plant systems actuation instrumentation channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9-2.
APPLICABILITY: As shown in Table 3.3.9-1.
ACTION:
With a plant system actuation instrumentation channel trip setpoint less a.
conservative than the value shown in the Allowable Value column of Table 3.3.9-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
g b.
With one or more plant systems actuation instrumentation channels l
inoperable, take the ACTION required by Table 3.3.9-1.
CLINTON.- UNIT 1 3/4 3-97 Amendment No. 49, 71 APR 9 1993
INSTRUMENTATION PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4.3.9.1 Each plant system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.9.1-1.
4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per 18 months.
1 CLINTON - UNIT I 3/4 3-98 Amendment No.40,7J,94
REACTOR COOLANT SYSTEM SAFETY / RELIEF VALVES SURVEILLANCE REQUIREMENTS 4.4.2.1.1 The acoustic monitor for each safety / relief valve shall be demonstrated OPERABLE by performance of a:
a.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and a b.
CHANNEL CALIBRATION at least once per 18 months.*
4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:
a.
CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least once per 92 days.
b.
CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST at least once per 18 months.
- The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
CLINTON - UNIT 1 3/4 4-10 Amendment No.BJ94
w t
SAFETY / RELIEF VALVES LOW-LOW SET FUNCTION LIMITING CONDITION FOR OPERATION 3.4.2.2 The low-low set function of the following reactor coolant system safety / relief valves shall be OPERABLE with the following settings *:
Low-Low Set function Setooint* (osia) i 15 osi Valve No.
Qp1D Close F051D 1033 926 F051C 1073 936 F047F 1113 946 F051B 1113 946 F051G 1113 946 l
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a.
With the low-low set function of one of the above required reactor coolant system safety / relief valves inoperable, restore the inoperable low-low set function to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With the low-low set function of more than one of the above required reactor coolant system safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With either low-low set function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2.2 The low-low set function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:
r a.
CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at least once per 92 days.
b.
CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST at least once per 18 months.
- 0ne channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the purpose of performing surveillance testing in accordance with Specification 4.4.2.2.
- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
CLINTON - UNIT 1 3/4 4-11 Amendment No.5,77,94
-