ML20064M159
| ML20064M159 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/05/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20064M161 | List: |
| References | |
| DPR-62-A-072, DPR-71-A-048 NUDOCS 8208260380 | |
| Download: ML20064M159 (20) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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CAROLINA POWER & LIGHT COMPANY DOCKET N0. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT N0.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power & Light Company dated November 13, 1980, with supplement dated November 17, 1981, complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulat'ons 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 Spec-ifications as indicated in the attachment to this license amendment
- and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8208260380 820805 PDR ADOCK 05000324 P
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.3.
This license amendment is effective as of the date of issuance.
1 1
FOR THE NUCL R REGULATORY COMMISSION Domenic B. Vassall,
ef Operating Reactors Branch #2 Division of Licensing 1
Attachment:
Changes to the Technical Specifications Date of Issuance: August 5,1982 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Remove the following pages and replace with identically numbered pages.
3/4 1-3 3/4 1-4 3/4 3-40 3/4 3-41 3/4 3-42 i
3/4 3-43 i
Add 3/4 3-43a 1
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REACTIVITY CONTROL SYSTEMS 3/4.1.3 CONTROL RODS CONTROL ROD OPERABILITY LIMITING CONDITION FOR OPERATION 3.1.3.1 All control rods shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With one control inoperable due to being immovable, as a result of a.
excessive friction or mechanical interference, or known to be untrippable:
1.
Within one hour:
a)
Verify that the inoperable control rod, if withdrawn, is separated from all other inoperable control rods by at least two control cells in all directions.
b)
Disarm the associated directional control valves hydraulically by closing the insert and withdraw isolation valves.
2.
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 />.
3.
Restore the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.
b.
With one or more control rods inoperable for causes other than addressed in ACTION a, above:
1.
If the inoperable control rod (s) is withdrawn, within one hour:
a)
Verify that the inoperable withdrawn control rod (s) is separated from all other inoperable control rods by at least two control cells in all directions, and b)
Demonstrate the insertion capability of the inoperable withdrawn control rod (s) by inserting the control rod (s) at least one notch by drive water pressure within the normal operating range *, or c)
Fully insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves either:
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust water isolation valves.
- The inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.
BRUNSWICK - UN T 1 3/4 1-3 Amendment No. 48
REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) 2.
If the inoperable control rod (s) is inserted:
a)
Within one hour disarm the associated directional control valves either:
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust water isolation valves.
b)
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 />.
c.
With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE at least once per 31 days by:*
a.
Verifying each valve to be open.
b.
Cycling each valve at least one complete cycle of full travel.
4.1.3.1.2 All withdrawn control rods not required to have their directional control valves disarmed electrically or hydrantically shall be demonstrated OPERABLE by moving each control rod at least one notch:
a.
At least once per 7 days when above the preset power level of the RWM and RSCS, and b.
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 above the preset power level of the RWM and RSCS and any control rod is immovable as a result of excessive friction or mechanical interference.
4.1.3.1.3 All withdrawn control rods shall be determined OPERABLE by demonstrating the scram discharge volume drain and vent valves OPERABLE when control rods are scram tested per Specification 4.1.3.2, by verifying that' the drain and vent valves:
a.
Close within 30 seconds af ter receipt of a signal for control rods to scram, and b.
Open when the scram signal is reset or the scram discharge volume trip is bypassed.
- These valves may be closed intermittently for testing under administrative control.
BRUNSWICK - UNIT 1 3/4 1-4 Amendment No. 48
as TABLE 3.3.4-1 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 5
O MINIMUM NUMBER OF APPLICABLE OPERABLE CHANNELS OPERATIONAL c:
TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM (a)
CONDITIONS d[
1.
APRM (C51-APRM-CH.A,B,C,D,E,F) a.
Upscale (Flow Biased) 2 1
b.
Inoperative 2
1,2,5 c.
Downscale 2
1 d.
Upscale (Fixed) 2 2, 5 2.
ROD BLOCK MONITOR (CSI-RBM-CH. A,B) a.
Upscale 1
1*
b.
Inoperative 1
1*
c.
Downscale 1
1*
s 3.
SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D) full in (b) 1 2, 5 a.
Detecto ot C
b.
Upscale 1
2, 5 Inoperati g )
c 1
2, 5 c.
d.
Downscale 1
2, 5 4.
INTERMEDIATE RANGE MONITORS (d) (C51-IRM-K601A,B,C,D,E,F,G,H) a.
Detector not full in (*)
2 2, 5 b.
Upscale 2
2, 5 Inoperably*)
2 2, 5 c.
d.
Downscale 2
2 I
g 5
SCRAM DISCHARGE VOLUME it a.
Water Level - High l#
1, 2, 5**
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TABLE 3.3.4-1 (Continu d)
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 a.
hours in one of the trip systems for maintenance and/or testing except for Rod Block Monitor function.
b.
This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.
This function is bypassed when the associated IRM channels are on range 8 c.
or higher.
d.
A total of 6 IRM instruments must by OPERABLE.
This function is bypassed when the IRM channels are on range 1.
e.
When THERMAL POWER exceeds the preset power level of the RWM and RSCS.
With any control rod withdrawn.
Not applicable to control rods removed 1
per Specification 3.9.10.1 or 3.9.10.2.
This signal is contained in the Channel A logic only.
BRUNSWICK - UNIT 1 3/4 3-41 Amendment No. 48
en TABLE 3.3.4-2 E
d CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS c
E 7:
TRIP FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWABLE VALUE I
c 1.
APRM (CSI-APRM-CH. A,B,C,D,E,F) a.
Upscale (Flow Biased)
< (0.66W + 42%)
T*
< (0.66W + 42%)
T*
MTPF
~
MTPF b.
Inoperative NA NA c.
Downscale
> 3/125 of full scale
> 3/125 of full scale d.
Upscale (Fixed)
T 12% of RATED THERMAL POWER T 12% of RATED THERMAL POWER 2.
ROD BLOCK MONITOR (CSI-RBM-CH.A,B) a.
Upscale
< (0.66W + 41%)
T*
< (0.66W + 41%)
T*
MTPF MTPF b.
Inoperative NA NA c.
Downscale
> 3/125 of full scale
> 3/125 of full scale 3.
SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D) a.
Detector not full in NA NA 5
5 b.
Upscale
< 1 x 10 cps
< 1 x 10 cp, 4
c.
Inoperative NA NA N
d.
Downscale
> 3 cps
> 3 cps 4.
INTERMEDIATE RANGE MONITORS (C51-IRM-K601A,B,C,D,E,F,C,H) a.
Detector not full in NA NA b.
Upscale
< 108/125 of full scale
< 108/125 of full scale c.
Inoperative NA NA d.
Downscale
> 3/125 of full scale
> 3/125 of full scale 5.
Water Ievel High
< 73 gallons
< 73 gallons Nm
- T=2.43 for 8x8 fuel E.
T=2.48 for 8x8R fuel l
T=2.48 for P8x8R fuel n
g TABLE 4.3.4-1 c
5 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5
O OPERATIONAL e
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH c
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED d
1.
APRM (C51-APRM-CH.A,B,C,D,E,F) a.
Upscale (Flow Biased)
NA S/U(C),M R(b)(a) g b.
Inoperative NA S/U(c),Q NA 1, 2, 5 c.
Downscale NA S/U(c)
,M NA(a) 1 l
d.
Upscale (Fixed)
NA S/U(c) 0 R
2, 5 2.
ROD BLOCK MONITOR (C51-RBM-CH.A,B) a.
Upscale NA S/U(c),g g(a) g, 2
b.
Inoperative NA S/U(c),0 NA(a) 1*
i c.
Downscale NA S/U(c)
,M R
g, Me 3.
SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D) b a.
Detector not full in NA S/U(c)
,W NA 2, 5 S/U((C) b.
Upscale NA
,W NA 2, 5 S/U c)
,W NA 2, 5 c.
Inoperative NA d.
Downscale NA S/U(c)
,W NA 2, 5 4.
INTERMEDIATE RANGE MONITORS (C51-IRM-K601A,B,C,D,E,F,G,H) a.
Detector not full in NA S/U(C),W(d)
NA 2
NA W
NA 5
b.
Upscale NA S/U(C),W(d)
NA 2
NA W
NA 5
k c.
Inoperative NA S/U(C),W(d)
NA 2
g NA W
NA 5
- s d.
Downscale NA S/U(C),W(d)
NA 2
,o NA W
NA 5
g TABLE 4.3.4-1 (Cont'd) c CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SIRVEILLANCE REOUIREMENTS O
CHANNEL OPERATIONAL s
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH g
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED 4
5.
Water Level - High NA Q
R 1, 2, 5**
a.
CHANNEL CALIBRATIONS are electronic.
b.
This calibration shall consist of the adjustment of the APRM flow biased setpoint to conform to a calibrated flow signal.
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.
c.
d.
When changing from CONDITION 1 to CONDITION 2, perform the required surveillance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering 00NDITION 2.
u, 3:
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
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o UNITED STATES
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NUCLEAR REGULATORY COMMISSION -
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company dated November 13, 1980, with supplement dated November 17, 1981, complies with the standards and requirenents 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby-amended to read as follows:
(2) T_echnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
i i
2 1
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION
/ft-A Domenic B. Vassal
, hief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 5,1982 e
r--
1
N ATTACHMENT TO LICENSE' AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET N0. 50-324 1
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4 1
de Remove the.following pages and replace with identically numbered pages.
3/4 1-3 3/41-4
,. J, 3/4 3-40 Il' 3/4 3-41 i n 3/4 3-42 s
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.A REACTIVITY CONTROL SYSTEHS i
3/4.1.2 CONTROL RODS 4
CONTROL ROD OPERABILITY LIMITING CONDITION FOR OPERATION 3.1.3.1 All control rods shall be'0PERABLE.
1 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
t ACTION:
a.
With one control rod inoperable due to being immovable, as a result of excessive friction or mechanical interference, or known to be untrippable:
i l.
Within one hour:
l a)
Verify that the inoperable control rod, if withdrawn, is j
separated from all other inoperable control rods by at least two control cells in all directions.
- k b)
Disarm the associated directional control valves hydraulically by closing the insert and withdraw isolation valves.
2.
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 />.
I 3.
Restore the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 />.
I b.
With one or more control rods inoperable for causes other than addressed in ACTION a, above:
I 1.
If the inoperable control rod (s) is withdrawn, within one hour:
)
a)
Verify that the inoperable withdrawn control rod (s) is separated from all other inoperable control rods by at least l
two control cells in all directions, and i
b)
Demonstrate the insertion capability of the inoperable withdrawn control rod (s);by inserting the control rod (s) at
(
least one notch by drive water pressure within the normal operating range *, or 1
c)
Fully insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves either:
1)
Electrically, or 1.
2)
Hydraulically by closing the drive water and exhaust water isolation valves.
l
- The inoperable control rod may then be withdrawn to a position no further withdrawn than its position when found to be inoperable.
BRUNSWICK - UNIT 2 3/4.1-3 Amendment No. 72 I
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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) 2.
If the inoperable control rod (s) is inserted:
a)
Within one hour disarm the associated directional control valves either:
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust water isolation valves.
b)
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 />.
c.
With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE at least once per 31 days by:*
a.
Verifying each valve to be open.
't b.
Cycling each valve at least one complete cycle of full travel.
4.1.3.1.2 All withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:
a i
A a.
At least once per 7 days when above the preset power level of the RWM and RSCS, and b.
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 above the preset power level of the RWM and RSCS and any control rod is immovable as a result of excessive friction or mechanical interference.
4.1.3.1.3 All withdrawn control rods shall be determined OPERABLE by demonstrating the scram discharge volume drain and vent valves OPERABLE, when control rods are scram tested per Specification 4.1.3.2, by verifying that the drain and vent valves:
a.
Close within 30 seconds af ter receipt of a signal for control rods to scram, and b.
Open when the scram signal is reset or the scram discharge volume trip is bypassed.
- These valves may be closed intermittently for testing under administrative control.
BRUNSWICK - UNIT 2 3/4 1-4 Amendment No. 72
tz TABLE 3.3.4-1 8
CONTROL ROD WITHDRAWAL BLOCK It,STRUMENTATION l
6 MINIMUM NUMBER OF APPLICABLE i
OPERABLE CHANN OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM CONDITIONS l
1.
APRM (C51-APRM-CH.A,B,C,D,E,F) a.
Upscale (Flow Biased) 2 1
b.
Inoperative 2
1,2,5 c.
Downscale 2
1 d.
Upscale (Fixed) 2 2, 5 2.
ROD BLOCK MONITOR (CSI-RBM-CH.A,B) a.
Upscale 1
1*
b.
Inoperative 1
1*
c.
Downscale 1
1*
4{
3 SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D) a.
Detecto ot full in( )
1 2, 5 b.
Upscale 1
2, 5 c) c.
Inoperati 1
2, 5 d.
Downscale 1
2, 5 4
INTERMEDIATE RANTE MONITORS (d) (C51-IRM-K601 A, B, C, D, E, F, G, H)
Detector not full in(*)
2 2, 5 a.
b.
Upscale 2
2, 5 Inoperablg 2
2, 5 c.
d.
Downscale 2
2, 5 5.
S.
a.
Water Level - High 1#
1, 2, 5**
Su rt
TABLE 3.3.4-1 (Continu d) 1 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 a.
hours in one of the trip systems for maintenance and/or testing except for Rod Block Monitor function.
b.
This function is bypassed if detector is reading >100 cps or the IRM channels are on range 3 or higher.
This function is bypassed when the associated IRM channels are on range 8 c.
or higher.
d.
A total of 6 IRM instruments must be OPERABLE.
This function is bypassed when the IRM channels are on range 1.
e.
)
This function is bypassed when the IRM channel's are on range 1.
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
This signal is contained in the Channel A logic only.
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BRUNSWICK - UNIT 2 3/4 3-41 Amendment No. 72
en TABLE 3.3.4-2
- n CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SETPOINTS s
O TRIli FUNCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWABLE VALUE i
1.
APRM (C51-APRM-CH.A,B,C,D,E,F) c:
N a.
Upscale (Flow Biased)
< (0.66 W + 42%)
T*
< (0.66 W + 42%)
T*
d MTPF MTPF b.
Inoperative NA NA c.
Downscale
> 3/125 of full scale
> 3/125 of full scale d.
Upscale (Fixed)
[12%ofRATEDTHERMALPOWER
[12%ofRATEDTHERMALPOWER 2.
ROD BLOCK MONITOR (C51-RBM-CH. A,B) a.
Upscale
< (0.66 W + 39%)
T*
< (0.66 W + 39%)
T*
MTPF MTPF b.
Inoperative NA NA c.
Downscale
> 3/125 of full scale
> 3/125 of full scale w
3.
SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D)
N w
a.
Detector not full in NA NA 5
5 E
b.
Upscale
~< 1 x 10 cps
-< 1 x 10 cp, c.
Inoperative NA NA d.
Downscale
> 3 cps
> 3 cps 4.
INTERMEDIATE RANGE MONITORS (C51-IRM-K601A,B,C,D, E,F,G,H) a.
Detector not full in NA NA b.
Upscale
< 108/125 of full scale
< 108/125 of full scale c.
Inoperative NA NA d.
Downscale
> 3/125 of full scale
> 3/125 of full scale 5.
Water Level High
_ 73 gallons
_ 73 gallons 8"
- T=2.60 for 7 x 7 fuel.
T=2.45 for 8 x 8 fuel.
T=2.48 for 8 x 8R fuel.
T=2.48 for P8 x 8R fuel.
.D
TABLE 4.3.4-1 8g CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5g CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REOUIRED 1.
APRM (CSI-APRM-CH.A,B,C,D,E,F) a.
Upscale (Flow Biased)
NA S/UIC)
R(b)(a) g M
S/U(c), Q b.
Inoperative NA NA 1, 2, 5 S/U(c), M c.
Downscale NA S/U(c), O NA(a) 1 d.
Upscale (Fixed)
NA R
2, 5 2.
ROD BLOCK MONITOR (C51-RBM-CH.A,B) a.
Upscale NA S/U(c) M R(a) g, S/U((C), Q b.
Inoperative NA S/U c), M NA(a) 1*
c.
Downscale NA R
g.
w N
3.
SOURCE RANGE MONITORS (C51-SRM-K600A,B,C,D) y a.
Detector not full in NA S/U(c) u W
NA 2, 5 S/U(c), W b.
Upscale NA NA 2, 5 S/U(c), W c.
Inoperative NA NA 2, 5 d.
Downscale NA S/UIC), W NA 2, 5 4.
INTERMEDIATE RANGE MONITORS (C51-IRM-K601A,B,C,D,E,F,G,H) a.
Detector not full in NA S/U(c), g(d)
E 2
NA W
NA 5
b.
Upscale NA S/U(c), g(d)
NA 2-NA W
NA 5
c.
Inoperative NA S/U(c), g(d)
NA 2
y NA W
NA 5
h d.
Downscale NA S/U(C), W(d)
NA 2
j NA W
E 5
.!?
a:
TABLE 4.3.4-1 (Cont'd) m E$
CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS cn l5 3
9 CHANNEL OPERATIONAL i
e CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH l
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED a
5.
a.
Water Leval - High NA Q
R 1, 2, 5**
a.
CHANNEL CALIBRATIONS are electronic.
b.
This calibration shall consist of the adjustment of the APRM flow biased setpoint to conform to a calibrated flow signal.
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.
When changing from CONDITION 1 to CONDITION 2o perform the required surveillance within 12 hous:s af ter entering CONDITION 2.
t' When THERMAL POWER is greater than tne preset power level of the RWM and RSCS.
With any control rod withdrawn. Not applicable to control rodo removed per Y'
Specification 3.9.10.1 or 3.9.10.2.
Ou a
it 8n
.