ML20079Q085
| ML20079Q085 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/08/1991 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079Q087 | List: |
| References | |
| NUDOCS 9111150180 | |
| Download: ML20079Q085 (14) | |
Text
~
l g' *%
j'\\
" J' /); f UN!TED STATES n
i NUCLEAR REGULATORY COMMISSION a
WASHINGTON D.c 20004 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (thelicensee),datedJune4,1991,complieswiththe standards and requirements of the Atomic Energy Act of 1954, as n
amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the 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 set forth in 10 CFR Chapter it 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 amendunt is in accordance witc 10 CFR Part 51 of the Commission's regulations and all applicable requirements have 'oeen satisfied.
2.
Accordingly, the license is amended by changes to the' Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
9111150100 911000 gDR-ADOCK _0000 3
2
(?) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised i
through Amendment No.
79, and the Environmental Protection Plan crntained in Appendix D, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
()A0 Richar'd Barrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Datt of 1ssuance:
October 8. 1991 l
-w--
r
,y---n,------.--,,-n..-m-..
-,n-.
g...,-,
.-.,--r y,
I ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. NPf.11 D0CKET NO. 50 373 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. Pages indicated with an asterisk sre provided for convenience, REMOVE INSERT 3/4 3 35 3/4 3 35 3/4 3 36 3/4 3 36
- 3/4 3 37 3/4 3 37 3/4 3 38 3/4 3 38
INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMEN1ATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.4.1 The anticipat.ed transient without scram recirculation pump trip (ATWS RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be OPERABLE 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 OPERABLE status with its trip setpointadjustedconsistentwith-theTripSetpointvalue, b.
With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) 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 />.
With the number of OPERABLE channels two or more less than required c.
by the Minimum OPERABLE Channels per Trip.'ystem requirement for one trip system and:
1.
If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both inoperable channels 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 />, or, if this action will initiate a pump trip, declare the trip-system inoperable.
2.
If the inoperable channell, include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperable.
d.
With one trip system inoperable, restore the inoperable trip system to OPERALLE 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, With both trip systems inoperable, restore at least one trip system e.
to OPERABLE status within *. hour 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 />.
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 CAllBRATION 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 4
all channels shall be performed at least once per 18 months.
LA SALLE - UNIT 1 3/4 3-35 Amendment No. 79 o
i TABLE 3.3.4.1-1 E
g ATWS RECIRCULATION PLMP TRIP FYSTEM INSTRUMENTATION i
?
r-MINIMUM 9PERABLE LS I
m
- . TRIP FUNCTION PER TRIP SYSTEM i
E I
i 1.
2 l
l
- Low Low, Level 2
[
y 2.
Pa.ctor Vessel Pressure-!!igh 2.
l T
T L.
L p-p i
i 1,
f
[
(a)One' channel in one trip system 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 f
[.
g surveillance provided that all ether char.aels are OFERABLE.
E i
}
1 1.
f k
8 4'
- m-i n
- s.
.n g
i e
2?
~
c W
[
t i
t i:
I t
,e r
w
=
w w-
..m..
TABLE 3.3.4.1-2 g
ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPOINTS P
rn TRIP ALLOWABLE e
TRIP FUNCTION SETPOINT VALUE C
1.
Reactor Vessel, Water Level -
1-50 inches
- 1-57 inches
- low Low, Level 2 2.
Reactor Vessel Pressure-High
< 1135 psig
< 1150 psig See Bases Figure B3/4 3-1.
R A
t:
l TABLE 4.3.4.1-I g
ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRLHENTATION SURVEILLANCE REQUIREMENTS G
m CHANNEL CHANNEL FUNCTIONAL CHANNEL TRIP FUNCTION CHECK TEST CALIBRATION C3
[
1.
S M
R Low Low, Level 2 2.
Reactor Vessel Pressure - High 5
M q
t i
U r.
%d 1
e i
i a
S Ei
l~e.,'o,,
/g UNITED STATES l
?.
NUCLEAR REGULATORY COMMISSION J
g wAsmNotoN, o.c. aoses
%..... J' COMMONWEALTH ED1 SON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT P AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. NPF-18 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated June 4, 1991, complies with the standards and requiremnts of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter 1; B.
The f acility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonabic assurance: (i)'thattheactivitiesauthorizedby 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 set forth in-10_CFR Chapter 1; 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 c this amendnent 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 tht; Technice'l Specifica-tions as indicated in the enclosure to this license amend:cht and paragraph 2.C.(2) of the Facility Operating License No. NPF-1P is hereby amended to read as follows:
i 2
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
63, and the Environmental Proter. tion Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance, to be implemented prior to the end of the next refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION 3
I db04 er J.
'arrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical St+cifications 06tt of Issuance:
October 8, 1991 l
l
m;,
ATTAq'?ENT TO LICENSE AMENDMENT NO.
63 FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are tuentified by amendment nunber and contain a vertical line indicating the area of change.
Pages indicated with an asterisk are provided for convenience REMOVE INSERT 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36
- 3/4 3-37
- 3/4 3-37 3/4 3-38 3/4 3-38
L~
INSTRUMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION 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 OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.1-2.
APPLICABIIITY:
OPERATIONAL CONDITION 1.
ACTION:
a.
With an ATWS recirculation pump trip system instrumentation channel trip seboint 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 OPERABLE 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 OPERABLE Channels aer Trip System requirement for one or both trip systems, ) lace tie inoperable channel (s) in the tripped condition within 1
- 1our, With the number of OPERABLE channels two or more less than required c.
by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
1.
If the inoperable channels conskt. of one reactor vessel water level channel and one reactor vessel pressure channel, place both inc,perable channels in the tripped condition within I hour, or, if this action will init3 ate a pump trip, declare the trip system inoperable.
2.
If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperable, d.
With one trip system inoperable, restore the inoperable trip system 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 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, With both trip systems-inoperable, restore at least one trip system e.
to OPERABLE status within I hour 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 />.
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, w
LA SALLE - UNIT 2 3/4 3-35.
Amendment Noi 63-
~
_ 1_ -
k
).
s 5
TABLE 3.3.4.1-1 vs l
ATVS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION E
t L
g MINTMUM OPERAPLE g LS l
q TRIP FUNCTION PER TRIP SYSTEM i
'l
\\
1.
2 l
l i
. Low Low,' Level 2 j
2.
Reactor Vessel Pressure-High 2
i l
[
i I
l I
w
-1 1
i
?
.Y t
x l
f i
i i:
3' r
E
[
1 3
i r-
.E '
O
(*)Dne channel.in one trip system 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 provided that all other channels are OPERABLE.
i-
TABLE 3.3.4.1-2 9
ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION SETPilINTS m?g TRIP ALLOVABLE TRIP FUNCTION SETPOINT VALUE C$,
1.
Reactor Vessel, Water Level -
1-50 inches
- 3-57 '
Low Low, Level 2
=
2.
Reactor Vessel Pressure-High 1 ?135 psig i ints psig i
i i
R.
Y$
i See Bases Figure B3/4 3-1.
I r-TABLE 4.3.4.1-1 ATWS RECIRCULATION PLMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL g.
TRIP FUNCTION CHECK TEST CALIBRATION
[
Z 1.
S M
R m
-Low Low, Level 2 2.
Reactor Vessel Pressure - High S
M Q
f L
f f
l i
w 1
t
[
i 3 -.
i
?
e i
i
.