ML20136G757
| ML20136G757 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 03/14/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20136G765 | List: |
| References | |
| NUDOCS 9703180188 | |
| Download: ML20136G757 (22) | |
Text
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UNITED STATES g
,j NUCLEAR REGULATORY COMMISSION
~
t WASHINGTON, D.C. 20066-0001 4.....,d 4
COMMONWEALTH EDISON COMPANY l
DOCKET N0. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.155 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated January 6, 1997, 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 i
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 s
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 I
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l 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. DPR-19 is hereby amended to read as follows:
9703180188 970314 PDR ADOCK 05000237 P
PDR i
(2)
Igshnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 155, are hereby incorporated in the license. The licensee shall operate the facility in accordance 1
with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION f\\
C' J A
ohn F. Stan, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14, 1997 t
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u UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 2066H001 44*****
,o COMMONWEALTH EDISON COMPANY DOCKET N0. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No. DPR-25 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated January 6,1997, 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 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
l B..
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
4 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION JodnF.Stang, enior Project Manager i
Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 14, 1997 i
1 1
' ATTACHMENT TO LICENSE AMENDMENT NOS. 155 AND 150 FACILITY OPERATING LICENSE NOS. DPR-19 AND DRP-25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.1-6 3/4.1-6 3/4.1-10 3/4.1-10 3/4.2-30 3/4.2-30 3/4.2-33 3/4.2-33 3/4.2-34 3/4.2-34 3/4.2-36 3/4.2-36 4
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3
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(
4 REACTOR PROTECTION SYSTEM RPS 3/4.1.A TABLE 3.1.A 1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION l
TABLE NOTATION i
-(a) 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 tripped condition provided at least one OPERABl.E CHANNEL in the same TRIP SYSTEM is monitoring that parameter.
(b) This function may be bypassed, provided a control rod block is actuated, for reactor protection system logic reset in Refuel and S.utdown positions of the reactor mode switch.
(c) Unless adequate SHUTDOWN MARGIN has been demonstrated per Specification 3/4.3.A and the "one-rod-out" Refuel mode switch interlock has been demonstrated OPERABLE per Specification 3.10.A, the " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn. However, this is not required for control rods removed per Specification 3.10.1 or 3.10.J.
-(d) With THERMAL POWER greater than or equal to 45% of RATED THERMAL POWER.
-(e) An APRM CHANNEL is inoperable if there are fewer than 2 LPRM inputs per level or there are less than 50% of the normal complement of LPRM inputs to an APRM CHANNEL.
(f) This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted j
or removed per Specification 3.12.A.
i (g) Required to be OPERABLE only prior to and during required SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
(h) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not
- required.
(i) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.10.1 or 3.10.J.
(j) This function is not required to be OPERABLE when reactor pressure is less than 600 psig.
i DRESDEN UNITS 2 & 3 3/4.1-6 Amendment Nos. 155 & 150
s REACTOR PROTECTION SYSTEM RPS 3/4.1.A TABLE 4.1.A 1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS (1) With THERMAL POWER greater than or equal to 45% of RATED THERMAL POWER.
(m) Required to be OPERABLE only prior to and during required SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
(n) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(o) The provisions of Specification 4.0.D are not applicable to the CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION surveillances for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering OPERATIONAL MODE 2 or 3 when shutting down from OPERATIONAL MODE 1.
(p) This function is not required to be OPERABLE when reactor pressure is less than 600 psig.
l (q) A current source provides an instrument channel alignment every 3 months.
DRESDEN UNITS 2 & 3 3/4.1-10 Amendment Nos. 155 & 150
_m.
TABLE 3.2.E-1 (Continued)
E m
_4 CONTROL ROD BLOCK INSTRUMENTATION E
5 z
.a 2i
(
Minimum Applicable (n
Trip CHANNEL (s) per OPERATIONAL 5
N Functuma: Unit Setooint Trio FunctionM MODE (s)
ACTION Z
sp w
1 SOURCE RANGE MONITORS a.
Detector rict fullinN NA 3
2e 51 2
58
.51 5
b.
Upscale" s1 x 10 cps 3
2 51 2
5 51 M
c.
Inoperative
.NA 3
2 51 2
5 51 w3
'u O
i INTERMEDIATE RANGE MONITORS o
a.
Detector not fullin NA 6
2, 5 51 b.
Upscale s108/125 6
2, 5 51 of full scale c.
Inoperative NA 6
2, 5 51 d.
Downscale" 25/125 6
2, 5 51 of full scale oo
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INSTRUMENTATION Control Rod Blocks 3/4.2.E TABLE 3.2.E-1 (Continued) 3 CONTROL ROD BLOCK INSTRUMENTATION i
i TABLE NOTATION (a) The RBM shall be automatically bypassed when a peripheral control rod is selected.
(b) This function shall be automatically bypassed if the IRM channels are on range 3 or higher.
4 I
(c) This function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.
(d) This function shall be automatically bypassed when the IRM channels are on range 1.
i (e) With THERMAL POWER 230% of RATED THERMAL POWER.
(f) With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.10.1 or 3.10.J.
(g) The Average Power Range Monitor rod block function is varied as a function of recirculation drive flow (W). The trip setting of this function must be maintained in accordance with Specification 3.11.B.
W is equal to the percentage of the drive flow required to produce a rated core flow of 98 x 105 j
lbs/hr.
(h) Required to be OPERABLE only during SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
I (i) 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 CHANNEL in the tripped condition provided the Functional Unit maintains control rod block capability.
(j) With detector count rate less than or equal to 100 cps.
l I
d DRESDEN - UNITS 2 & 3 3/4.2-33 Amendment Nos. 155 & 150
TABLE 4.2.E-1 o
M CONTROL ROD BLOCK INSTRUMENTATION h
o SURVEILLANCE REQUIREMENTS z
K E
c CHANNEL Applicable h CHANNEL FUNCTIONAL CHANNEL OPERATIONAL to Functional Unit CHECK TEST CAllBRATION
MODEls) 5 ro z
IP W
L ROD BLOCK MONITORS a.
Upscale NA S/U *', M" Q
1" S
b.
Inoperative NA S/U d, M" NA 1"
S c.
Downscale NA S/U 8, M" Q.
1*
S L AVERAGE POWER RANGE MONITORS w
a.
Flow Biased Neutron Flux - High w
1.
Dual Recirculation Loop Operation NA S/U", M SA 1
2.
Single Recirculation Loop Operation NA S/U", M SA 1
b.
Inoperative NA S/U", M NA 1,2,5 8 S
c.
Downscale NA S/U, M Q
1 d.
Startup Neutron Flux - High NA S/U", M SA 2, 5' L SCURCE RANGE MONITORS N
3 a.
Detector not full in"'
NA S/U", W E
2"*, S 3
o
{
b.
Upscale'd NA S/U", W E
2", 5 s
o c.
Inoperative'd NA S/U, W NA 2",5 S
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5 m
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-. ~... - - -. - -. -. - - -. -. _. - _. - - - - - -.. - -....
lNSTRUMENTATION Control Rod Blocks 3/4.2.E' 4
4 TABLE 4.2.E-1 (Continued) i j
CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS j
TABLE NOTATION j
l (a) Neutron detectors may be excluded from CHANNEL CAllBRATION.
j (b) Within 7 days prior to startup.
(c). Includes reactor manual control " relay select matrix" system input.
-(d) With THERMAL POWER 230% of RATED THERMAL POWER.
(e) With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.10.1 or 3.10.J.
2 (f) This function shall be automatically bypassed if the IRM channels are on range 3 or higher.
i (g) This function shall be automatically bypassed when the associated IRM channels are on range 8 or l
higher.
1 (h) This function shall be automatically bypassed when the IRM channels are on range 1.
(i) The provisions of Specification 4.0.D are not applicable to the CHANNEL FUNCTIONAL TEST and j
' CHANNEL CALIBRATION surveillances for entry into the applicable OPERATIONAL MODE (s) from l
OPERATIONAL MODE 1 provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.
(j) Required to be OPERABLE only during SHUTDOWN MARGIN demonstrations performed per l
Specification 3.12.B.
i (k) With detector count rate less than or equal to 100 cps, i
1 4
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DRESDEN - UNITS 2 & 3 3/4.2-36 Amendment Nos. 155 & 150
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1 UNITED STATES s
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20666 4001 COMMONWEALTH EDIS0N COMPANY AND MIDAMERICAN ENERGY COMPANY DOCKET N0. 50-254 i
OUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICf25.E Amendment No. 174 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 6, 1997, complies with the standards and 4
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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION s*
Robert M. Pulsife, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14, 1997 l
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 0
2 WASHINGTON, D.C. 20066-0001
...../
COMMONWEALTH EDIS0N COMPANY NW MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 OVAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 170 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 6, 1997, 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
c 3 0 B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 170, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
4 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
4 FOR THE NUCLEAR REGULATORY COMMISSION o
Robert M. Pulsifer, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 14, 1997 i
t i
3 ATTACHMENT TO LICENSE AMENDMENT NOS.174 AND 17n FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.1-6 3/4.1-6 3/4.1-10 3/4.1-10 3/4.2-31 3/4.2-31 3/4.2-34 3/4.2-34 3/4.2-35 3/4.2-35 3/4.2-37 3/4.2-37 I
i i
i I
REACTOR PROTECTION SYSTEM RPS 3/4.1.A i
TABLE 3.1.A-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATION _
(a) 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 tripped condition provided at least one OPERABLE CHANNEL in the same TRIP SYSTEM is monitoring that parameter.
(b) This function may be bypassed, provided a control rod block is actuated, for reactor protection system logic reset in Refuel and Shutdown positions of the reactor mode switch.
(c) Unless adequate SHUTDOWN MARGIN has been demonstrated per Specification 3/4.3.A and the "one-rod-out" Refuel mode switch interlock has been demonstrated OPERABLE per Specification 3.10.A, the " shorting liaks" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn. However, this is not required for control rods removed per Specification 3.10.1 or 3.10.J.
(d) With THERMAL POWER greater than or equal to 45% of RATED THERMAL POWER.
(e) An APRM CHANNEL is inoperable if there are fewer than 2 LPRM inputs per level or there are less than 50% of the normal complement of LPRM inputs to an APRM CHANNEL.
(f) This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification 3.12.A.
(g) Required to be OPERABLE only prior to and during required SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
(h) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(i) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.10.1 or 3.10.J.
QUAD CITIES-UNITS 1 & 2 3/4.1-6 Amendment Nos. 174 8 170
REACTOR PROTECTION SYSTEM RPS 3/4.1.A 1
TABLE 4.1.A-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS I
q (1) With THERMAL POWER greater than or equal to 45% of RATED THERMAL POWER.
i (m) Required to be OPERABLE only prior to and during required SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
(n) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(o) The provisions of Specification 4.0.D are not applicable to the CHANNEL FUNCTIONAL TEST 4
and CHANNEL CAllBRATION surveillances for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering OPERATIONAL MODE 2 or 3 when shutting down from OPERATIONAL MODE 1.
I (p) A current source provides an instrument channel alignment every 3 months.
i' i
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I' 1
4 1
4 I
QUAD CITIES-UNITS 1 & 2 3/4.1-10 Amendment Nos. 174 8 170
____.____m
=
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TABLE 3.2.E-1 (Continued) z C
y>
-4 CONTROL ROD BLOCK INSTRUMENTATION U
k.
m Z
i U) '
Minimum Applicable.
z Trip CHANNEL (s) per OPERATIONAL 5
A Functxmal Und Setooint Trio Function
- MODE (s)
ACTION Z
us 1 SOURCE RANGE MONITORS sp 9
a.
Detector not fullin" NA 3
28 51 2
50 51 M
5 b.
Upscale s1 x 10 cps 3
2 51 2
5 51 W
c.
Inoperative NA 3
2 51 2
5 51 r
M i
so 4) i INTERMEDIATE RANGE MONITORS i
a.
Detector not full in NA 6
2, 5 51
~
b.
Upscale s108/125 6
2, 5 51 of full scale c.
Inopera'tive NA 6
2, 5 51
-i d.
Downscale" 23/125 6
2, 5 51 of full scale l
n O
a a
e.
e
~3 3
0 O
3 E
e cn l
3 O~
l z
e o
a ca l
C b
o.
.m o
F
INSTRUMENTATION Control Rod Blocks 3/4.2.E I
TABLE 3.2.E-1 (Continued) i i
CONTROL ROD BLOCK INSTRUMENTATION i
TABLE NOTATION 4
(a) The RBM shall be automatically bypassed when a peripheral control rod is selected.
(b) - This function shall be automatically bypassed if the IRM channels are on range 3 or higher.
j I.
(c) This function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.
(d) This function shall be automatically bypassed when the IRM channels are on range 1.
l
' (e) With THERMAL POWER 230% of RATED THERMAL POWER.
i (f) With more than one control rod withdrawn. Not applicable to control rods removed per Specification j
3.10.1 or 3.10.J.
j (g) The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow j
(W). The trip setting of this function must be maintained in accordance with Specificanon 3.11.B. W is equal to the percentage of the drive flow required to produce a rated core flow of 98 x 10 lbs/hr.
8
)
(h) Required to be OPERABLE only during SHUTDOWN MARGIN demonstrations performed per i
Specification 3.12.B.
(i) 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 CHANNEL in the tripped condition provided the Functional Unit maintains control rod block capability.
1 l
(j) With detector count rate less than or equal to 100 cps.
J I
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e i
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i QUAD CITIES - UNITS 1 & 2 3/4.2-34 Amendment Nos. 174 8 170 4
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. - ~ ~.
TABLE 4.2.E-1 O
E E
CONTROL ROD BLOCK INSTRUMENTATION O
SURVEILLANCE REQUIREMENTS h
CHANNEL Applicable i
y CHANNEL FUNCTIONAL CHANNEL OPERATIONAL D
z Functional Unit CHECK TEST CALIBRATION
MODEls)
U 9
12 tn -
?
L ROD BLOCK MONITORS i
a.
Upscale NA S/U"", M'd Q
l'8 b.
Inoperative NA S/U d, Mid NA 1'd
.i S
I c.
Downscale NA S/USd M'd O
l '8 i
1 AVERAGE POWER RANGE MONITORS w
a.
Flow Biased Neutron Flux - High A
h 1.
Dual Recirculation Loop Operation NA S/U",M SA 1
w 1
2.
Single Recirculation Loop Operation NA S/U", M SA 1
I b.
Inoperative NA S/U*i, M NA 1,2,58 I
i c.
Downscale NA S/U", M SA 1
[
d.
Startup Neutron Rux - High NA S/U",M SA 2, 58
{
f 1 SOURCE RANGE MONITORS a.
Detector not full in"'
NA S/U", W E
2"*, SN 3
O-l 3
b.
Upscale'8 NA S/U*', W E
2, 5 I
a O
3 c.
Inoperative'8 NA S/U", W NA 2*, 5
[
O b.
- m m
O
INSTRUMENTATION Control Rod Blocks 3/4.2.E 1
e TABLE 4.2.E-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION 4
SURVEILLANCE REQUIREMENTS 4
TABLE NOTATION 4
(a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b) Within 7 days prior to startup.
(c) includes reactor manual control" relay select matrix" system input.
(d) With THERMAL POWER 230% of RATED THERMAL POWER.
(e) With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.10.1 or 3.10.J.
j (f) This function shall be automatically bypassed if the IRM channels are on range 3 or higher, (g) This function shall be automatically bypassed when the ast,ociated IRM channels are on range 8 or higher.
l (h) This function shall be automatically bypassed whcn the IRM channels are on range 1.
(i) The provisions of Specification 4.0.D are not applicable to the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION surveillances for entry into the applicable OPERATIONAL MODE (s) from OPERATIONAL MODE 1 provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.
1 (j) Required to be OPERABLE only during SHUTDOWN MARGIN demonstrations performed per Specification 3.12.B.
i
]
(k) With detector count rate less than or equal to 100 cps.
i 1
t QUAD CITIES - UNITS 1 & 2 3/4.2-37 Amendment Nos. 174 & 170