ML20135J121
| ML20135J121 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 09/20/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20135J122 | List: |
| References | |
| NUDOCS 8509250285 | |
| Download: ML20135J121 (21) | |
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UNITED STATES E
NUCLEAR REGULATORY COMMISSION s
f wasmwoTom, p. c, rosss
......o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. NPF-11 1.
The Nuclear Regulatory Cosmission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Comonwealth Edison Company, dated July 15, 1985 and supplemented by letters dated August 9 and 12, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Consission's regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance:
(1) 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 set forth in 10 CFR Chapter I; O.
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 amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 24 and the Environmental Protection Plan contained in Aspendix B, are hereby incorporated in the license.
The licensee s1all operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
!DR 73 P
POR
3.
This amendment is effective as of its date of issuance.
l FOR THE NUCLEAR REGULATORY COPMISSION
,0 Walter R. Butler, Chief Licensing Branch No. 2 i
Division of Licensing
Enclosure:
i Changes to the Technical Specifications Date of Issuance: SEP 2 01985 1
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A t
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~ ENCLOSURE TO LICENSE AMEN 0 MENT NO. pa FACILITY OPERATING LICENSE NO. NPF-11
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DOCKET NO. 50-373 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 1
l 3/4 3-1 3/4 3-1 i
3/4 3-8 3/4 3-8 3/4 3-23 3/4 3-23 3/4 3-32 3/4 3-32 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 J
3/4 3-89 3/4 3-89 3/4 3-90 3/4 3-90 j
3/4 3-92 3/4 3-92 3/4 4-6 3/4 4-6 1
i 3/4 4-9 3/4 4-9 j
3/4 6-7 3/4 6-7 3/4 6-34 3/4 6-34 j
3/4 8-4 3/4 8-4 3/4 8-17 3/4 8-17 3/4 8-28 3/4 8-28 r
3/4 8-29 3/4 8-29 i
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- - - - -, ~ -. - -. - _
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEN INSTRUNENTATION LINITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERA 8tE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
APPLICA8ILITY:
As shown in Table 3.3.1-1.
t ACTION:
i i
a.
With the number of OPERA 8LE channels less than required by the Minimus j
OPERA 8LE Channels per Trip System requirement for one trip system, place that trip system in the tripped condition
- within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The provisions 3
of Specification 3.0.4 are not applicable.
b.
With the the number of OPERA 8LE channels less than required by the Minimum OPERA 8LE Channels per Trip System requirement for both trip systems, l
place at least one trip system ** in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
]j and take the ACTION required by Table 3.3.1-1.
j SURVEILLANCE REQUIRENENTS j
4.3.1.1 Each reactor protection system instrumentation channel shall be i
demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL I
TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at j
the frequencies shown in Table 4.3.1.1-1.
1 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of l
all channels shall be performed at least once per 18 months.***
i 4
l 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its j
limit at least once per 18 months.
Each test shall include at least one channel 1
{
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 i
reactor trip system.
1 s
l With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip t
Function to occur.
In these cases, the inoperable channel shall be restored i
to OPERA 8LE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1
{
for that Trip Function shall be taken.
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If more channels are inoperable in one trip system than in the other, select that trip system to place in the tripped condition, except when this would j
cause the Trip Function to occur.
{
- The specified 18-month interval may be waived for Cycle 1 provided the l
surveillance is performed during Refuel 1.
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4 i
LA SALLE - UNIT 1 3/4 3-1 Amendment No. 24
TABLE 4.3.1.1-1 (Continued) l Q
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS m
N l;;
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL ~ UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRED c3 i
8.
Scram Discharge Volume Water H
Level - High NA M
R 1, 2, 5 l
9.
Turbine Stop Valve - Closure MA M
R 1
10.
Turbine Control Valve Fast closure Valve Trip System Oil Pressure - Low NA M
R*
1 l
11.
Reactor Mode Switch Shutdown Position NA R'
NA 1,2,3,4,5 w
A
- 12. Manual Scram NA M
NA 1,2,3,4,5 Y
=
(a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b) The IRM, and SRM channels shall be determined to overlap for at least 1/2 decades during each startup and the IRM and APRM channels shall be determined to overlap for at least 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.
(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION.I when THERMAL POWER > 25% of RATED THERMAL POWER.
Adjust the APRM channel if the absolute difference is greater than 2%.
Any APRM channel gain adjustment made in compliance with Specification 3.2.2 shall not be included in determining the absolute difference.
(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a f
calibrated flow signal.
(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP
=
I system.
g (g) Measure and compare core flow to rated core flow.
(h) This calibration shall consist of verifying the 6 1 1 second simulated thermal power time constant.
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5 "The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
INSTRUMENTATION 3/4.3.3 EMERGENCY CORE CO3 LING 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 OPERA 8LE 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.
APPLICA8ILITY:
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 Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERA 8LE 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 "A" or "B" inoperable, restore the c.
inoperable trip system to OPERABLE status within:
1.
7 days, provided that the HPCS and RCIC systems are OPERABLE.
2.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
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 done pressure to less than or equal to 122 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 REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERA 8LE 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 4.3.3.1-1.
4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.*
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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.
"The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1, for LPCI A, B, and C.
l LASALLE UNIT-1 3/4 3-23 Amendment No. 24
TABLE 4.3.3.1-1 E
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS u,
?
G; CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH lE TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED
_4 Ed A. DIVISION I TRIP SYSTEM
Low Low Low, Level 1 NA M
R 1, 2, 3, 4*,.5*
b.
Drywell Pressure - High NA M
-Q 1,2,3 c.
LPCS Pump Discharge Flow-Low NA M
Q 1, 2, 3, 4*, 5*
d.
LPCS and LPCI A Injection Valve J
Injection Line Pressure Low Interlock NA M
R 1, 2, 3, 4*, 5*
s-e.
LPCS and LPCI A Injection Valve
((
Reactor Pressure Low Interlock NA M
R 1, 2, 3, 4*, 5*
g, f.
LPCI Pump A Start Time Delay Relay NA M
Q 1, 2, 3, 4*, 5*
h>
g.
LPCI Pump A Flow-Low NA M
Q 1, 2, 3, 4*, 5*
h.
Manual Initiation NA R***
NA 1, 2, 3, 4*, 5*
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- 2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"#
a.
Low Low Low, Level 1 NA M
R 1,2,3 b.
Drywell Pressure-High NA M
Q 1,2,3 I
c.
ADS Timer NA
.M Q
1,2,3 d.
Low, Level 3 NA M
R 1,2,3 e.
LPCS Pump Discharge-y Pressure-High NA M
Q 1,2,3 5,
f.
LPCI Pump A Discharge e
Pressure-High NA M
Q 1,2,3 3
g.
Manual Initiation NA R
NA 1,2,3 3
e
.O
i TABLE 4.3.3.1-1 (Continued) b EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREMENTS i
F m
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH E
TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED l
4 e
B. DIVISION 2 TRIP SYSTEM t
Low Low Low, Level 1 NA M
R 1, 2, 3, 4*, 5*
b.
Drywell Pressure - High NA M
Q 1,2,3 c.
LPCI B and C Injection Valve Injection Line Pressure Low Interlock NA M
R 1, 2, 3, 4*, 5*
[
d.
LPCI Pump B Start Time Delay Relay NA M
Q 1, 2, 3, 4*, 5*
R e.
LPCI Pump Discharge Flow-Low NA M
Q 1, 2, 3, 4*, 5*
f.
Manual Initiation NA R***
NA 1, 2, 3, 4*, 5*
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g.
LPCI B and C Injection Valve
.O Reactor Pressure Low Interlock NA M
R 1, 2, 3, 4*,
Sa
- 2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B"#
a.
Low Low Low, Level 1 NA M
R 1,2,3 i
b.
Drywell Pressure-High NA M
Q 1,2,3 c.
ADS Timer NA M
Q 1, 2, 3 d.
-l Low, Level 3 NA M
R 1,2,3 i
e.
LPCS Pump B and C Discharge i
Pressure-High NA M
Q 1,2,3 k
f.
Manual Initiation NA R
NA 1,2,3 a
c h
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1 TABLE 4.3.3.1-1 (Cont'.inued)
E EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS i
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED H
H C. DIVISION 3 TRIP SYSTEM
- 1. HPCS SYSTEM a.
Low Low, Level 2 NA M
R 1,2,3,4*,5*
b.
Drywell Pressure-High NA M
Q 1, 2, 3 c.
Reactor Vessel Water Level-High Level 8 NA M
R 1, 2, 3, 4*, 5*
d.
Condensate Storage Tank Level -
Low NA M
Q 1,2,3,4*,5*
,g e.
Suppression Pool Water Level - High NA M
Q 1, 2, 3, 4*, 5*
J, f.
Pump Discharge Pressure-High NA M
Q 1, 2, 3, 4*, 5*
g.
HPCS System Flow Rate-Low NA M
Q
- 1. 2, 3, 4*, 5*
h.
Manual Initiation NA R
NA 1, 2, 3, 4*, 58 D. LOSS OF POWER 4 1.
4.16 kv Emergency Bus Under-voltage (Loss of Voltage)
NA NA R
1, 2, 3, 4**, 5**
- Not required to be OPERABLE when reactor steam done pressure is less than or equal to 122 psig.
- When the system is required to be OPERABLE after being manually realigned, as applicable, per Specification 3.5.2.
g
- Required when ESF equipment is required to be OPERA 8LE.
3
- The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during 3
Refuel 1.
g g
INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION 3.3.4.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT) system-instrumentation channels shown in Table 3.3.4.1-1 shall be OPERA 8LE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.1-2.
APPLICABILITY:
OPERATIONAL CONDITION 1.
ACTION:
a.
With an ATWS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.4.1-2, declare the channel inoperable until the channel is restored to OPERA 8LE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels one less than required by the Minimum OPERA 8LE Channels requirement for one trip function in one trip system, restore the inoperable channel to OPERABLE status within 14 days or be in at least STARTUP within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.3.4.1.1 Each ATWS recirculation pump trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.1-1.
4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.*
g
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"The specified 18-month interval may be waived for Cycle'l provided the surveillance is performed during Refuel 1.
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LA SALLE - UNIT 1 3/4 3-35 Amendment No. 24 i
TABLE 4.3.7.11-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS P
OPERATIONAL CHANNEL' CONDITIONS FOR CHANNEL SOURCE FUNCTIONAL CHANNEL WHICH SURVEIL-E INSTRUMENT CHECK CHECK TEST CALIBRATION LANCE REQUIRED Q
s 1.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EFFLUENT MONITORING SYSTEM a.
Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release O
D Q(1)
R(3)***
l 2.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.
Hydrogen Monitor D
N.A.
M Q(4) w 3.
MAIN STACK MONITORING SYSTEM S
a.
Noble Gas Activity Monitor 0
M Q(5)
R(3) b.
Iodine Sampier W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Efflueni System Flow Rate Monitor D
N.A.
Q R
e.
Sampler Flow Rate Monitor D
N.A.
Q R
4.
CONDENSER AIR EJECTOR RADI0 ACTIVITY MONITOR a.
Noble Gas Activity Monitor D
'M Q(2)
R(3) 5.
SBGTS MONITORING SYSTEM N
a.
Noble Gas Activity Monitor D
M Q(S)
R(3) b.
Iodine Samp1er W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
,N.A.
N.A.
N.A.
d.
Effluent System Flow Rate Monitor D
N.A.
Q R
y e.
Sampler Flow Rate Monitor D
N.A.
Q R
TABLE 4.3.7.11-1 (Continued)
TABLE NOTATION At all times.
During main condenser offgas treatment system operation.
The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
During operation of the main condenser air ejector.
During operation cf the SBGTS.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation capability of this pathway, and that control room alarm annunciation occurs if any of the following conditions exists:
(each channel will be tested independently so as not to initiate automatic isolation during operation).
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Loss of power.
3.
Instrument alarms on downscale failure.
4.
Instrument controls not set in Operate or High Voltage mode.
(Auto-matic isolation shall be demonstrated during th'e CHANNEL CALIBRATION.)
(2) The CHANNEL FUNCTIONAL TEST for the log scale monitor shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Loss of' power.
3.
Instrument alarms on downscale failure.
4.
Instrument controls not set in Operate or High Voltage mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference radioactive standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall permit calibrating the system over its intended range of I
energy and measurement range.
For subsequent CHANNEL CALIBRATION, the l
initial reference radioactive standards or radioactive sources that have been related to the initial calibration shall be used.
(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:
1.
One volume percent hydrogen, balance nftrogen, and 2.
Four volume percent hydrogen, balance nitrogen.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
l 3.
Instrument controls not set in the Operate mode.
LASALLE UNIT-1 3/4 3-90 Amendment No. 24
INSTRUMENTATION 3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 The feedwater/ main turbine trip system actuation instrumentation channels shown in Table 3.3.8-1 shall be OPERA 8LE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.8-2.
APPLICABILITY: OPERATIONAL CONDITION 1.
ACTION:
a.
With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.8-2, declare the channel inoperable and either place the inoperable channel in the tripped condition until the channel is restored to OPERA 8LE status with its-trip setpoint adjusted consistent with the Trip Setpoint value, or declare the associated system inoperable.
b.
With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channel to OPERABLE status within 7 days or be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With the number of OPERABLE channels two less than required by the Minimum OPERA 8LE Channels per Trip System requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least STARTUP within the next 6 hcurs.
SURVEILLANCE REQUIREMENTS I
4.3.8.1 Each feedwater/ main turbine trip system actuation instrumentation channel shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALI8 RATION operations at the frequencies shown in Table 4.3.8.1-1.
4.3.8.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.*
l i
"The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
l LASALLE UNIT-1
~3/4 3-92 Amendment No. 24 l
1
REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE
~.
LEAKAGE DETECTION SYSTEMS LINITING CONDITION FOR OPERATION
+
3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERA 8LE:
The primary containment atmosphere particulate radioactivity a.
monitoring system, b.
The primary containment sump flow monitoring system, and c.
Either the primary containment air coolers condensate flow rate monitoring system or the primary containment atmosphere gaseous radioactivity monitoring system.
APPLICA8ILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With only two of the above required leakage detection systems OPERABLE, opera-tion may continue for up to 30 days provided grab samples"of the containment l
atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required i
gaseous and/or particulate radioactive monitoring system is inoperable; other-wise, 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 l
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 4.4.3.1 The reactor coolant system detection systems shall be demonstrated OPERA 8LE by:
i Primary containment atmosphere particulate and gaseous monitoring a.
systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a l
CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL 1
l CALIBRATION at least once per 18 months.
b.
Primary containment sump flow monitoring system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL j
CALIBRATION TEST at least once per 18 months.*
l i
i c.
Primary containment air coolers condensate flow rate monitoring p
system performance of a CHANNEL FUNCTIQNAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
"The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
l l
LA SALLE-UNIT 1 3/4 4-6 Amendment-No. 24
TABLE 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES SYSTEM VALVE NUMBER FUNCTION a.
LPCS E21-F006 LPCS Injection E-21-F005*
LPCS Injection l
b.
HPCS E22-F005 HPCS Injection E22-F004 HPCS Injection c.
RHR E12-F041A LPCI Injection E12-F0418 LPCI Injection E12-F041C LPCI Injection E12-F042A LPCI Injection E12-F0428*
LPCI Injection E12-F042C*
LPCI Injection E12-F050A Shutdown Cooling Return E12-F0508 Shutdown Cooling Return E12-F053A Shutdown Cooling Return E12-F0538*
Shutdown Cooling Return E12-F009 Shutdown Cooling Suction E12-F008 Shutdown Cooling Suction d.
RDIC E51-F066 RCIC Head Spray E51-F065 RCIC Head Spray
- The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
l LA SALLE-UNIT 1 3/4 4-9 Amendment No. 24
CONTAINMENT SYSTEMS MSIV LEAKAGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.4 Two independent MSIV leakage control systems (LCS) shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
With one MSIV leakage control system inoperable, restore the inoperable system to OPERA 8LE status within 30 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 />.
SURVEILLANCE REQUIREMENTS 4.6.1.4 Each MSIV. leakage control system shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Starting the blower (s) from the control room and operating the blower (s) for at least 15 minutes, 2.
Energizing the heaters and verifying. a current of 8.28 amperes i 10% per phase for each heater.
b.
During each COLD SHUTDOWN in accordance with Specification 4.0.5.
c.
At least once per 18 months
- by:
l 1.
Performance of a functional test which includes simulated actuation of the system throughout its operating sequence, and verifying that each automatic valve actuates to its correct position and the blower starts.
1 1
2.
Verifying that the blower develops at least the below required vacuum at the rated capacity:
a)
Inboard valves, 15" H O at 100 scfm.
2 b)
Outboard valves, 60" H O at 200 scfm.
2 d.
By verifying the flow, pressure and, temperature operating instrumentation to be OPERA 8LE by performance of a:
1.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and 2.
CHANNEL CALIBRATION at least once per 18 months.
"The specified 18 month interval may be waived for Cycle 1 provided the l
surveillance is performed during Refuel 1.
LA SALLE - UNIT 1 3/4 6-7 Amendment No.24 1
1 4
TABLE 3.6.3-1 (Continued) i E
PRIMARY CONTAINNENT ISOLATION VALVES 1
>{
VALVE FUNCTION AND NUISER Other Isolation valves (Continued) i J
E 7.
1HG001A, B 1HG002A, 8 4
1 1HG005A, B I
1HG006A, B 8.
Standby Liquid Control System IC41-F004A, B 1
1C41-F007 9.
Reactor Recirculation Seal Injection ***
Id)
~
1833-F013A, B wi 1B33-F017A,B(I) i
?
10.
Drywell Pneumatic System IIN018 i
But > 3 seconds.
I (a) See lpecificption 3.3.2, Table 3.3.2-1, for. isolation signal (s) that operates each valve group.
(b) Not included in total sum of Type B and C tests.
(c) May be opened on an intermittent basis under administrative control.
(d) Not closed by SLCS actuation.
l (e) Not closed by Trip Functions Sa, b or c, Specification 3.3.2, Table 3.3.2-1.
(f) Not closed by Trip Functions 4a, c, d, e or f of Specification 3.3.2, Table 3.3.2-1.
(g) Not subject to Type C leakage test.
(h) Opens on an isolation signal.
Valves will be open during Type A test.
No Type C test required.
(1) Also closed by drywell pressure-high signal.
{
(j) Hydraulic leak test at 43.6 psig.
2 (k) Not subject to Type C leakage test - leakage rate tested per Specification 4.4.3.2.2.
g (1) These penetrations are provided with removable spools outboard of the outboard isolation valve.
During operation, these lines will be blind flanged using a double 0-ring and a type B leak s
test.
In addition, the packing of these isolation valves will be soap-bubble tested to ensure f
insignificant or no leakage at the containment test pressure each refueling outage.
'o These valves shall have a maximum isolation time of 40 seconds until STARTUP following the r*
first refueling outage.
- The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
4 i
ELECTRICAL POWER SYSTEMS
{
SURVEILLANCE REQUIREMENTS (Continued) d.
At least once per 18 months
- during shutdown by:
l 1.
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service.
l 2.
Verifying the diesel generator capability to reject a load of f
greater than or equal to 1190 kw for diesel generator 0, greater l
than or equal to 638 kw for diesel generators lA and 2A, and greater than or equal to 2381 kw for diesel generator 1B while 2
maintaining engine speed less than or equal to 75% of the difference between nominal speed and the overspeed trip setpoint or 155 above nominal, whichever is less.
3.
Verifying the diesel generator capability to reject a load of i
2600 kw without tripping.
The generator voltage shall not exceed 5000 volts during and following the load rejection.
4.
Simulating a loss of offsite power by itself, and:
a)
For Divisions 1 and 2 and for Unit 2 Division 2:
1)
Verifying de-energization of the emergency busses and load shedding from the emergency, busses.
2)
Verifying the diesel generator starts on the auto-start l
signal, energizes the emergency busses with permanently i
connected loads within 13 seconds, energizes the auto-connected loads and operates for greater than or equal to 5 minutes while its generator is so loaded.
After j
energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 i 150 volts and 60 1 1.2 Hz during this test.
b)
For Division 3:
1)
Verifying de energization of the emergency bus.
2)
Verifying the diesel generator starts on the auto-start l-signal, energizes the emergency bus with its loads with-in 13 seconds and operates for greater than or equal to 5 minutes while its generator is so loaded.
After energization, the steady state voltage and frequency of the emergency bus shall be maintained at 4160 i 150 volts and 60 1 1.2 Hz during this test.
5.
Verifying that on an ECCS actuation test signal, without loss of offsite power, diesel generators 0, IA and 18 start on the auto-start signal and operate on standby for greater than or equal to 5 minutes.
The generator voltage and frequency shall be 4160 + 416, -150 volts and 60 + 3.0, -1.2 Hz within 13 seconds after the auto-start signal; the steady state generator voltage and frequency shall be maintained within these limits during this test.
"The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
i LASALLE-UNIT 1 3/4 8-4 Amendment No. 24
ELECTRICAL POWER SYSTEMS i
SURVEILLANCE REQUIREMENTS (Continued) b)
Division 2, greater than or equal to:
i 1) 488.5 amperes for the first 60 seconds, I
2) 237.6 amperes for the next 14 minutes, 3) 177.6 amperes for the next 15 minutes, and 4) 141.6 amperes for the next 30 minutes, and 5) 54.4 amperes for the last 180 minutes.
c)
Division 3, greater than or equal to*:
l 1) 58.4 amperes for the first 60 seconds, 2) 11.1 amperes for the next 239 minutes.
d)
Unit 2 Division 2, greater than or equal to:
1) 488.5 amperes for the first 60 seconds, 2) 237.6 amperes for the next 14 minutes, 3) 177.6 amperes for the next 15 minutes, 4) 141.6 amperes for the next 30 minutes, and 5) 54.4 amperes for the last 180 minutes.
e.
At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80% of the manufacturers rating when subjected to a performance discharge test. Once per 60 month interval, i
this performance discharge test may be performed in lieu of the i
battery service test.
s f.
Annual performance discharge tests of battery capacity shall be j
given to any battery that shows signs of degradation or has reached t
8SE of the service life expected for the application.
Degradation
[
j is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.
I 4
i i
I l
"The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
LASALLE-UNIT 1 3/4 8-17 Amendment No. 24
TABLE 3.8.3.31 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES BYPASS DEVICE SYSTEM (S)
VALVE NUPEER (Continuous)(Accident Conditions)
AFFECTED e.
1821 - F020 Continuous Main steam system 1821 - F068 Continuous 1821 - F070 Continuous 1821 - F069 Continuous 1821 - F071 Continuous 1821 - F072 Continuous 1821 - F073 Continuous f.
1821 - F065A Continuous Main feedwater system 1821 - F0658 Continuous g.
1E21 - F001 Continuous LPCS system 1E21 - F005 Accident Conditions i
1E21 - F011 Accident Conditions 1E21 - F012 Accident Conditions h.
IC41 - F001A Accident Conditions S8LCS IC41 - F0018 Accident Conditions 1.
1G33 - F001 Accident Conditions RWCU l
1G33 - F004 Accident Conditions l
j.
1E12 - F052A*
Accident Conditions RHR system 1E12 - F064A*
Accident Conditions 1E12 - F087A*
Accident Conditions 1E12 - F004A Continuous IE12 - F047A Continuous l
1E12 - F048A*
Accident Conditions I
1E12 - F003A Continuous i
1E12 - F026A*
Accident Conditions 1E12 - F068A continuous IE12 - F073A Continuous 1E12 - F074A Continuous i
1E12 - F011A*
Accident Conditions 1E12 - F024A*
Accident Conditions 1E12 - F016A*
Accident Conditions 1E12 - F017A*
Accident Conditions 1E12 - F027A*
Accident Conditions l
1E12 - F0048 Continuous IE12 - F0478 Continuous i
1E12 - F0488*
Accident Conditions I
1E12 - F0038 Continuous IE12 - F0688 Continuous 1E12 - F0738 Continuous IE12 - F0748 Continuous IE12 - F0268*
Accident Conditions 1E12 - F0118*
Accident Conditions l
"The specified 18 month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.
LASALLE-UNIT 1 3/4 8-28 Amendment No. 24
TABLE 3.8.3.31 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD
{
PROTECTION AND/0R BYPASS DEVICES BYPASS DEVICE SYSTEM (S)
VALVE NUMBER (Continuous)(Accident Conditions)
AFFECTED j.
1E12 - F0248" Accident Conditions RHR system l
1E12 - F0068 Continuous 1E12 - F0168*
Accident Conditions 1E12 - F0178*
Accident Conditions j
IE12 - F0428*
Accident Conditions 1E12 - F0648*
Accident Conditions 1E12 - F093 Continuous IE12 - F021*
Accident Conditions i
i IE12 - F004C Continuous 1E12 - F0528*
Accident Conditions 1E12 - F0878*
Accident Conditions 1E12 - F0998*
Accident Conditions 1E12 - F099A*
Accident Conditions 1E12 - F008 Accident Conditions 1E12 - F009 Accident Conditions IE12 - F040A*
Accident Conditions 1E12 - F0408*
Accider.t Conditions 1E12 - F049A*
Accident Conditions
~
~
1E12 - F0498*
Accident Conditions 1
i 1E12 - F053A Accident Conditions IE12 - F0538 Accident Conditions 1E12 - F006A Continuous 1E12 - F023 Accident Conditions IE12 - F0278*
Accident Conditions l
IE12 - F042A*
Accident Conditions l
1E12 - F042C*
Accident Conditions i
1E12 - F064C*
Accident Conditions l
1E12 - F094 Continuous l
k.
1E51 - F086 Accident Conditions RCIC system 1E51 - F022 Accident Conditions IE51 - F068 Continuous 1E51 - F069 Continuous 1E51 - F080 Accident Conditions 1E51 - F046 Accident Conditions i
j 1E51 - F059 Accident Conditions 1E51 - F063 Accident Conditions 1E51 - F019 Accident Conditions i
1E51 - F031 Continuous
)
1E51 - F045 Accident Conditions 1
1E51 - F008 Accident Conditions I
1E51 - F010 Accident Conditions 1E51 - F013 Accident Conditions 1
1E51 - F064 Accident Conditions IE51 - F076 Accident Conditions "The specified 18 month interval may be waived for Cycle 1 provided the l
surveillance is performed during Refuel 1.
I I
l LASALLE-UNIT 1 3/4 8-29
' Amendment No. 24 i
- - -