ML17164A541
| ML17164A541 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  (NPF-014, NPF-022) |
| Issue date: | 01/09/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Pennsylvania Power & Light Co, Allegheny Electric Cooperative |
| Shared Package | |
| ML17164A542 | List: |
| References | |
| NPF-14-A-140, NPF-22-A-110 NUDOCS 9501310116 | |
| Download: ML17164A541 (33) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-387 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
>4O License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power Light Company, dated September 26,
- 1994, complies with the standards and, requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 I; 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.
950i3iOii6 9'50i09 PDR ADOCK 05000387 PDR Ji
f ~i)~
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
140 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPKL 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 and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 9, 1995 oh
. Stol z, Direct r ject Directorate I-2
'sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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ATTACHMENT TO LICENSE AMENDMENT NO. 140 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 3-2 3/4 3-5 3/4 3-7 3/4 3-8 3/4 3-52 3/4 3-53 3/4 3-55 3/4 3-56 INSERT 3/4 3-2 3/4 3-5 3/4 3-7 3/4 3-8 3/4 3-52 3/4 3-53 3/4 3-55 3/4 3-56
0)C CAO x
ZZ I
Z FUNCTIONALUNIT 1.
Intermediate Range Monitors:. (bl a.
Neutron Flux - High APPLICABLE OPERATIONAL CONDITIONS MINIMUMOPERABLE CHANNELS PER TRIP SYSTEM 2
3,4 5(c) 3 2
3(d)
TABLE 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION CD O
CD b.
Inoperative 2.
Average Power Range Monitor(el a.
Neutron Flux - Upscale, Setdown b.
Flow Biased Simulated Thermal Power-Upscale c.
Neutron Flux - Upscale 2
3,4 5
2 3
5(c)())
3 2
3(d) 2 2
2(d) d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reactor Vessel Water Level - Low, Level 3 5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation - High 1
2 3
5(c)())
1,2 2(()
2 2
2(d)
(Continued)
(a)
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 without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
Upon determination that a trip setpoint cannot be restored to within its specified value during performance of the CHANNEL CALIBRATION,the appropriate ACTION, 3.3.1a or 3.3.1b, shall be followed.
(b)
This function is automatically bypassed when the reactor mode switch is in the Run position.
(c)
The "shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn and shutdown margin demonstrations performed per Specification 3.10.3.
(d)
The non-coincident NMS reactor trip function logic is such that all channels go to both trip systems.
Therefore, when the "shorting links" are
- removed, the Minimum OPERABLE Channels Per Trip System is 4 APRMS and 6 IRMS.
(e)
An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 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 3.10.1.
(g)
This function is automatically bypassed when the reactor mode switch is not in the Run position.
(h)
This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(i)
With any control rod withdrawn."
(j)
This function shall be automatically bypassed when turbine first stage pressure is less than 108 psig or 17% of the value of first stage pressure in psia at valves wide open (V.W.O.) steam flow, equivalent to THERMAL POWER of about 24'/o of RATED THERMALPOWER.
(k)
Also actuates the EOC-RPT system.
(I)
This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.
Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
SUSQUEHANNA - UNIT 1 3/4 3-5 Amendment No. Xl')I 140
V)C CO QC Z
zz I
Cz FUNCTIONALUNIT 1.
a.
Neutron Flux - High b.
Inoperative CHANNEL CHECK S/U,S, S
NA CHANNEL FUNCTIONALTEST S/UI",W W
S/U'",W CHANNEL CALIBRATION
'A SA NA OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCEREQUIRED 2
3, 4, 5 2, 3, 4, 5 TABLE4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATIONSURVEILLANCEREQUIREMENTS 2.
Avg. Power Range Monitor a.
Neutron Flux-Upscale, Setdown S/U,S,'"
S S/u'",W W
SA SA 2
3 5lk)
Ca) b.
Flow Biased Simulated Thermal Power - Upscale S,D"'/u"',Q WI"II I SA RI"I c.
Fixed Neutron Flux - Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reactor Vessel Water Level-Low, Level 3 5.
Main Steam Line Isolation Valve-Closure 6.
Main Steam Line Radiation-High 7.
Drywell Pressure
- High NA NA S/u"I,Q S/U Q
0 NA Q
Q Q
W,SA NA Q
0 1,2,3,5'"'.2 1.2 1,2'2 C)
I I
coC co0Cmx z.z I
Cz FUNCTIONALUNIT 8.
Scram Discharge Volume Water Level - High CHANNEL CHECK CHANNEL FUNCTIONALTEST CHANNELCALIBRATION'"
OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCEREQUIRED TABLE4.3.1.1-1 {Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATIONSURVEILLANCEREQUIREMENTS a.
Level Transmitter b.
Float Switch 9.
Turbine Stop Valve - Closure NA NA NA 0
0 0
R R
CDa CD C)
- 10. Turbine Control Valve Fast Closure Valve Trip System Oil Pressure - Low
- 11. Reactor Mode Switch Shutdown Position
- 12. Manual Scram NA 0
W NA 1,2,3,4,5 1,2,3,4,5 (a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
The IRM and SRM channels shall be determined to overlap for at least 0.5 decades during each startup after enterjng OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 0.5 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, it 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 1 when THERMALPOWER 2 25% of RATED THERMALPOWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMALPOWER. 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 calibrated flow signal.
(f)
The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.
(g)
Verify measured core flow to be greater than or equal to established core flow at the existing loop flow.
(h)
This calibration shall consist of verifying the 6 2 1 second simulated thermal power time constant.
(i)
This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.
(j)
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(k)
This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed by Specification 3.10.3.
,g' i
~l 1
CoC Co0C z
zz I
Cz CD CD Ql ID TRIP FUNCTION 1.
ROD BLOCK MONITOR a.
Upscale b.
Inoperative c.
Downscale 2.
APRM a.
Flow Biased Neutron Flux - Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup 3.
SOURCE RANGE MONITORS a.
Detector not full in Ib) b.
Upscale c.
Inoperative (c) d.
Downscale ld) 4.
INTERMEDIATERANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale (e) 5.
Water Level-High TABLE 3.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION MINIMUMOPERABLE CHANNELS PER TRIP FUNCTION 4
4 3
2 3
2 3
2 3
2I t%
APPLICABLE OPERATIONAL CONDITIONS 1'l 1~
1 1,2,5'"
1 2 5II) 2,5 2,5 2,5 2,5 1,2,5'~
ACTION 60 60 60 61 61 61 61 61 61 61 61 61 61 61 61'1 61 61 61 62 6.
REACTOR COOLANT SYSTEM RECIRCULATIONFLOW a.
Upscale b.
Inoperative c.
Comparator 62 62 62
N B,GIm ACTION 60 -
Declare the RBM inoperable and take the ACTION required by Specification 3.1.4.3.
ACTION 61 With the number of OPERABLE Channels:
- a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
- b. Two or more less than required by the Minimum OPERABLE Channels per. Trip Function requirement, place at least one inoperable channel 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 />.
ACTION 62 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel 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 THERMALPOWER 2 30% of RATED THERMALPOWER.
With more than one control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
Not required when eight or fewer fuel assemblies (adjacent to the SRMs) are in the core.
a.
The RBM shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30% of RATED THERMALPOWER, b.
This function shall be automatically bypassed if detector count rate is 2 100 cps or the IRM channels are on range 3 or higher.
c.
This function is automatically bypassed when the associated IRM channels are on range 8 or higher.
d.
This function is automatically bypassed when the IRM channels are on range 3 or higher.
e.
This function is automatically bypassed when the IRM.channels are on range 1.
f.
This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.
SUSQUEHANNA - UNIT 1 3/4 3-53 Amendment No.~~t i40
V) co QCx zz I
Cz TRIP FUNCTION 1.
ROD BLOCK MONITOR a.
Upscale b.
Inoperative c.
Downscale CHANNELCHECK CHANNEL FUNCTIONALTEST CHANNEL CALIBRATION"'A NA NA s/u'b' SIUIb)'M s/u'"',M 0
NA 0
TABLE4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATIONSURVEILLANCEREQUIREMENTS OPERATIONALCONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1"
1" 1"
2.
APRM a.
Flow Biased Neutron Flux-Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup 3.
SOURCE RANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale 4.
INTERMEDIATERANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale 6.
Water Level-High 6.
REACTOR COOLANT SYSTEM RECIRCULATIONFLOW a.
Upscale b.
Inoperative c.
Comparator s
NA s
s NA NA NA NA NA s
NA s
NA NA NA NA s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'",w s/u'b',w s/u'b',w s/u'b',w s/u'",M s/u(b)'M s/u'",M SA NA SA SA NA 0
NA 0
NA Q
NA Q
Q NA 0
2,5 2,5 2,5 2,5 2,5 2,5 2,5 2,5 1
1 1
l g V't
(Continued)
(a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
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.
'ith THERMALPOWER 2 30% of RATED THERMALPOWER.
"" With more than one control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.
SUSQUEHANNA - UNIT 1 3/4 3-56 Amendment No. i9~ >40
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 110 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power III Light Company, dated September 26,
- 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 I; 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 Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
110 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPEL 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 and is to be implemented within 30 days after its date of issuance.
FOR THE NUCLEAR R ULATORY COMMISSION T
oh
. Stolz, Dire t r ject Directorate
-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation A'ttachment:
Changes to the Technical Specifications Date of Issuance:
January 9, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 110 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 3-2 3/4 3-5 3/4 3-7 3/4 3-8 3/4 3-52 3/4 3-53 3/4 3-55 3/4 3-56 INSERT 3/4 3-2 3/4 3-5 3/4 3-7 3/4 3-8 3/4 3-52 3/4 3-53 3/4 3-55 3/4 3-56
~ I r ~
V)C V)0C x
ZZ I
CZ FUNCTIONALUNIT 1.
Intermediate Range Monitors:. (b) a.
Neutron Flux - High APPLICABLE OPERATIONAL CONDITIONS MINIMUMOPERABLE CHANNELS PER TRIP SYSTEM 2
3,4 5(c) 3 2
3(d)
TABLE3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION CD CD b.
Inoperative 2.
Average Power Range Monitor(e) a.
Neutron Flux - Upscale, Setdown b.
Flow Biased Simulated Thermal Power-Upscale c.
Neutron Flux - Upscale 2
3,4 5
2 3
(c)(O 3
2 3(d) 2 2
2(d) d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reactor Vessel Water Level - Low, Level 3 1,2 3
5(c)(O 1
2(f) 1,2 2
2 2(d) 5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation - High 2(f)
~ E
(a)
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 without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
Upon determination that a trip setpoint cannot be restored to within its specified value during performance of the CHANNEL CALIBRATION,the appropriate ACTION, 3.3.1a or 3.3.1b, shall be followed.
k (b)
This function is automatically bypassed when the reactor mode switch is in the Run position.
(c)
The "shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn and shutdown margin demonstrations performed per Specification 3.10.3.
(d)
The non-coincident NMS reactor trip function logic is such that all channels go to both trip systems.
Therefore, when the "shorting links" are
- removed, the Minimum OPERABLE Channels Per Trip System is 4 APRIVIS and 6 IRMS.
(e)
An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 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 3.10.1.
(g)
This function is automatically bypassed when the reactor mode switch is not in the Run position.
(h)
This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITYis not required.
(i)
With any control rod withdrawn."
(j)
This function shall not be automatically bypassed when turbine first stage pressure is greater than an allowable value of 136 psig.
(k)
Also actuates the EOC-RPT system.
(I)
This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.
Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.
SUSQUEHANNA-UNIT2 3/4 3-5 Amendment No. H4 lH>>>0
(o V)
QCm zz I
Cz FUNCTIONALUNIT 1.
a.
Neutron Flux - High b.
Inoperative CHANNEL CHECK s/u,s,'"
S NA CHANNEL FUNCTIONALTEST s/u'",w W
s/UI',w CHANNELCALIBRATION'"
SA SA NA OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCEREQUIRED 2
3, 4, 5 2, 3, 4, 5 TABLE4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATIONSURVEILLANCEREQUIREMENTS G0
~O CD 2.
Avg. Power Range Monitor a.
Neutron Flux-Upscale, Setdown b.
Flow Biased Simulated Thermal Power - Upscale s/u,s, S
S Dig) s/u",w W
s/u'",Q SA SA W(d)le) SA Rlh) 2 3 5lk) c.
Fixed Neutron Flux - Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reactor Vessel Water Level-Low, Level 3 5.
Main Steam Line Isolation Valve-Closure 6.
Main Steam Line Radiation - High 7.
Drywall Pressure - High NA NA NA NA s/u'",Q s/u",Q Q
Q Q
Q Wld),SA NA Q
Q 1,2,3,5 1.2 1,2 1,2'.2
coC CA0C Z
zz Cz FUNCTIONALUNIT 8.
Scram Discharge Volume Water Level - High CHANNEL CHECK CHANNEL FUNCTIONALTEST CHANNELCALIBRATION"'PERATIONAL CONDITIONS FOR WHICH SURVEILLANCEREQUIRED TABLE4.3.1.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATIONSURVEILLANCEREQUIR=MENTS 1
a.
Level Transmitter b.
Float Switch 9.
Turbine Stop Valve - Closure NA NA 0
0.
0 R
R CD co
- 10. Turbine Control Valve Fast Closure Valve Trip System Oil Pressure
- Low
- 11. Reactor Mode Switch Shutdown Position
- 12. Manual Scram NA NA NA 0
W R
NA 1,2,3,4,5 1,2,3,4,5 O
e (a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
The IRM and SRM channels shall be determined to overlap for at least 0.5 decades during each startup afte entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 0.5 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, it 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 1 when THERMALPOWER 2 25% of RATED THERMALPOWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMALPOWER. 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 calibrated flow signal.
(f)
The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.
(g)
Verify measured core flow to be greater than or equal to established core flow at the existing loop flow.
(h)
This calibration shall consist of verifying the 6 2 1 second simulated thermal power time constant.
(i)
This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.
(j)
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
iki This funotion is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed by Speoifieation 3.t0.3.
~ ~
V)
V)0C x
zz I
Cz TRIP FUNCTION 1.
ROD BLOCK MONITOR a.
Upscale b.
Inoperative c.
Downscale 2.
APRM a.
Flow Biased Neutron Flux - Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup 3.
SOURCE RANGE MONITORS a.
Detector not full in (b) b.
Upscale (c) c.
Inoperative d.
Downscale (d) 4.
INTERMEDIATERANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale (el 6.
Water Level-High TABLE 3.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION MINIMUMOPERABLE CHANNELS PER TRIP FUNCTION 2
2 2
4 4
4 3
2 3
2 3
2 3
6 6
6 6
APPLICABLE OPERATIONAL CONDITIONS 1"
1" 1"
1 1,2,5'"
1 2 5IO 2
5 2
5 2
5 2
5 2,5 2,5 2,5 2,5 1,2,5" ACTION 60 60 60 61 61 61 61 61 61 61 61 61 61 61 61 61 61 61 61 62 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale b.
Inoperative c.
Comparator 62 62 62
I
~
I
hGIIQH ACTION 60 -
Declare the RBM inoperable and take the ACTION required by Specification 3.1.4.3.
ACTION 61 With the number of OPERABLE Channels:
- a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
- b. Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel 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 />.
ACTION 62 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel 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 THERMALPOWER 2 30% of RATED THERMALPOWER.
With more than one control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
Not required when eight or fewer fuel assemblies (adjacent to the SRMs) are in the core.
(a)
The RBM shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30% of RATED THERMALPOWER, (b)
This function shall be automatically bypassed if detector count rate is 2 100 cps or the IRM channels are on range 3 or higher.
(c)
This function is automatically bypassed when the associated IRM channels are on range 8 or higher.
(d)
This function is automatically bypassed when the IRM channels are on range 3 or higher.
(e)
This function is automatically bypassed when the IRM channels are on range 1
~
(f)
This function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.
SUSQUEHANNA - UNIT2 3/4 3-53 Amendment No.gg, 110
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U)C V)0Cmx zz I
Cz TRIP FUNCTION 1 ~
ROD BLOCK MONITOR a.
Upscale b.
Inoperative c.
Downscale CHANNEL CHECK CHANNEL FUNCTIONALTEST CHANNEL CALIBRATION" NA NA NA S/U,M S/U,M s/u'",M SA NA SA TABLE4.3.6-1 CONTROL ROD BLOCK INSTRUMENTATIONSURVEILLANCEREQUIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1"
1 l CD Ql Ol 2.
APRM a.
Flow Biased Neutron Flux-Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup 3.
SOURCE RANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale 4.
INTERMEDIATERANGE MONITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale 6.
Water Level-High 6.
REACTOR COOLANTSYSTEM RECIRCULATIONFLOW a.
Upscale b.
Inoperative c.
Cornparator S
NA S
S NA NA NA NA NA S
NA S
NA NA NA s/u'",w s/u'b',w s/u'",w s/u'",w s/u'",w s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'b',w s/u'",w s/u'b',w Q
s/u'b' s/u'",M s/UI",M SA NA SA SA NA SA NA SA NA SA NA SA Q
NA Q
1 1 2 5~~~
1 54%%
2,5 2,5 2,5 2,5 2,5 2,5 2,5 2,5 1,2,5~ ~
0 4'~
h
(a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
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.
" With THERMALPOWER 2 30% of RATED THERMALPOWER.
"'ith more than one control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10,2.
""'his function is required to be OPERABLE only prior to and during Shutdown Margin demonstrations as performed per Specification 3.10.3.
SUSQUEHANNA - UNIT2 3/4 3-56 Amendment No.
g 4
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