ML20141A993
| ML20141A993 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-062, DPR-071) |
| Issue date: | 03/26/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20141A998 | List: |
| References | |
| DPR-62-A-121, DPR-71-A-096 NUDOCS 8604040603 | |
| Download: ML20141A993 (14) | |
Text
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fg UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 3
j WASHINGTON, D. C. 20555
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1_
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power A Light Company (the licensee) dated July 1, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 (1) that the activities authorized by this amendment can be cuducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be iniraical 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 Comiss'on's regulations and all applhable 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. DPR-71 is
- I hereby amended to read as follows:
8604040603 860326 PDR ADOCK 05000324 P
2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 96, 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 of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,' n
/
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1986 l
9 e
4 4
4 ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-71 DCCKET NO. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3/4 3-7 3/4 3-Sa 3/4 3-43 4
3/4 3-43a g
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TABLE 4.3.1-1 e,,
REACTOR PROTECTION S STEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED N
1.
Intermediate Range Monitorst (C51-IRM-K601A,B,C,D,E,F,C,H) a.
Neutros. Flux - High D
S/U(b)(c), g(d)
R 2
D W
R 3,4,5 b.
Inoperative.
NA W(d)
NA 2,3,4,5 l
2.
Average Power Range Monitor:
(CSI-APRM-CH.A,B,C,D,E,F) a.
Neutron Flux - High 15%
S S/U(b)(m), g(d)
Q 2
S W(n)
Q 5
b.
Flow-Biased Neutron Flux - High S
S/U(b),y g(e)(f),q y
c.
Fixed Neutron Flux - High, 120%
S S/U(b),y g(e),q 3
W ")I")
NA 1, 2, 5 I
d.
Inoperative NA e.
Downscale NA W
NA 1
f.
LPRM D
NA (g) 1, 2, 5 3.
Reactor Vessel Steam Dome Pressure - High Ik)
II)
(B21-PT-NO23A,B,C,D)
NA NA R
1, 2 E.
(B21-PTM-N023A-1,B-1,C-1,D-1)
D M
M 1, 2 I
f, 4.
- n Lov, Level 1 (B21-LT-N017A-1,B-1,C-1,D-1)
NA(k) NA R
1, 2 II)
(B21-L'IN-N017A-1,B-1,C-1,D-1)
D M
M 1, 2 E
.E s
a
ts TABLE 4.3.1-1 (Continued)
Z h
REAC't0R PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS N
i (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.
(c) The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL 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 /> af ter entering OPERATIONAL CONDITION 2.
(e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.
'f (f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a i
calibrated flow signal.
(g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.
(h) This calibration shall consist of a physical inspection and actuation of these position switches.
(i) Instrument alignment using a standard current source.
(j)Calkbrationusingastandardradiationsource.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter y
check is not required.
8{
(1) Transmitters are exempted from the monthly channel' calibration.
n (m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of performing 1
5 the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
E (n) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing p
the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
1 TABLE 4.3.4-1 w
- n h
CONTROL ROD WITNDRAWAL BIACK INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
Q CHANNEL OPERATIONAL l
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH 11IP FUNCTION AND INSTRUMENT NtDfBER CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 1.
APRM (C51-APRM-CH.A,B,C,D,E,F) a.
Upscale (Flow Biased)
NA S/U(c)
R(b)(a) g S/U(c)(E
,q(f)
NA 1, 2, 5 l,
b.
Inoperative NA c.
Downscale NA S/U(c)
S/U(c)(E
,q(d)(f) yR a) 2, 5 l
g d.
Upscals (Fixed)
NA 2.
ROD BLOCK HOWITOR (C51-3BM-CH.A,B)
S/U(c)
R ")
1*
I S/U(c),H w
a.
Upscale NA l
)
b.
Inoperative NA S/U(c),q R a) g, y
3, w
c.
Downscale NA
,M S-3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D) a.
Detector not full in NA S/U(c)IC),y(d) j NA 2, 5 W(d)
NA 2, 5 1
b.
Upscale NA S/U S/U(C),W((d)
I i
c.
Inoperative NA NA 2, 5 S/U c),y d) j d.
Downscale NA NA 2, 5
,~
4.
INTERMEDIATE RANCE MONITORS (C51-IRM-K601A,B,C,D,E,F,G,H)
(c)(e),y(d) l s.
Detector not full in NA S
NA 2
NA W
NA 5
b.
Upscale NA S/U(c),y(d) h NA 2
e NA W
NA 5
o
- n c.
Inoperative NA S/UIC),W(d)
NA 2
NA W
NA 5
ton i
d.
Downscale NA S/U(c),y(d)
NA 2
NA W
NA 5
)
t
~
L 3
i TABLE 4.3.4-1 (cont'd) es I
Al I
h CONTRCL ROD WITHDRAWAL BIDCK INSTRLMENTATION SURVEILLANCE REQUIRENENTS s
CHANNEL OPERATIONAL j
Q CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH CALIBRATION (a)
SURVEILLANCE REQUIRED l
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK TEST g
N SCRAM DISCHARGE VOLUME (C11-LSH-N013E) 5.
R 1, 2, 5**
Water Level - High NA Q
j a.
When THERMAL POWER is greater than the preset power level of the RWM and RSCS.
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(a) CHANNEL CALIBRATIONS are electronic.
(b) This calibration shall consist of the adjustment of the APRM flow biased setpoint w
to conform to a calibrated flow signal.
i 2
(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 OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the w
S.
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 OPERATIONAL CONDITION 2.
E (e) Placement of Reactor Mode Switch into the Startup/ Hot Standby positica is permitted for the purpose of performing the required surveillance prior to withdrawal of control rods for the purpose of bringing l
the reactor to criticality.
~
(f) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of i
performing the required surveillance provided all control rods are fully inserted and the vessel head j
1 bolts are tensioned.
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UNITED STATES g'
3 NUCLEAR REGULATORY COMMISSION g
r WASHING TON, D. C. 20SM
- \\...../
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No.121 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commissicn) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated July 1,1985, complies with the standards and requirements of the Atomic Energy Act cf 1954, as amended (the Act) and the Commission's rules and regulation:; 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 regulttions; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the l
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, i
and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.121, 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 of issuance.
FOR THE NUCLEAR REGULATORY COMISSION YA Daniel R. Muller, Director BWRProjectDirectorate#2 Division of.BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 26, 1986 O
-l i
l ATTACHMENT TO LICENSE AMENDMENT NO. 121 FACILITY OPERATING LICENSE NO. DPR-62 i'
DOCKET N0. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3/4 3-7 3/4 3-8a 3/4 3-43 3/4 3-43a 2
1 b
4 Y
1 4
TABLE 4.3.1-1 ass f
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5
-Q CHANNEL OPERATIONAL FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH i
AND INSTRUMENT NUMBER CHECK TEST '
CALIBRATION (a)
SURVEILLANCE REQUIRED g
1.
(C51-IRM-K601A,B,C,D,E,F,C,H) a.
Neutron Flux - High D
S/U(b)(c), g(d)
'R 2
D W
R 3, 4, 5 b.
Inoperative NA W(d)
NA 2,3,4,5 2.
Average Power Range Monitor (C51-APRM-CH.A,B,C,D,E,F) u w
a.
Neutron Flux - High 15%
S S/U(b)(m), g(d)
Q 2
b W ")
Q 5
I S
b.
Flow-Biased Neutron Flux - High S
S/U(b),y g(e)(f),q y
~
c.
Fixed Neutron Flux - High, 120%
S S/U(b),y g(e),q y
d.
Inoperative NA W(")I")
NA 1,2,5 NA W
NA 1
e.
Downscale
' -D f.
.LPRM NA (g) 1, 2, 5
'~
/
~
3.
Reactor Yessel Steam Dome g
Pressure - High II')
II)
(B21-PT-NO23A,B,C,D)
NA
. NA R
1, 2 e
E.
(B21-PTM-NO23A-1,B-1,C-1,D-1)
D M
M 1, 2 b
i E
4.
- z:
Low, Level 1 E
(B21-LT-NOl7A-1,B-1,C-1,D-1)
NA(k) NA R
1, 2 II)
(B21-LTM-NOl7A-1,B-1,C-1,D-1)
D M
M 1, 2
s TABLE 4.3.1-1 (Continued) w REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS un N
R t
(a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
E (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.
y (c) The IRM channels shall be compared to the APRM chan'nels and the SRM instruments for overlap during each startup, if not performed within the previous 7 days.
(d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL 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 OPERATIONAL CONDITION 2.
(e) This calibration shall consist of the adjustment of the APRM readout to conform to the power values calculated by a heat balance during OPERATIONAL. CONDITION 1 when THERMAL POWER is greater than or equal w
to 25% of RATED THERMAL POWER.
5 (f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a w
h calibrated flow signal.
(g) The LPRMs shall be calibrated at least once per effective full power month (EFPM) using the TIP system.
(h) This calibration shall consist of a physical inspection and actuation of these position switches.
(1) Instrument alignment using a standard current source.
(j) Calibration using a standard radiation source.
4 (k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter g
check is not required.
g g.
(1) Transmitters are exempted from the monthly channel calibration.
m E
(m) Placement of Reactor Mode Swich into the Startup/ Hot Standby position is permitted for the purpose of performing y
the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
to
[,
(n) Placement of Reactor Mode Switch into the Shutdown.or Refuel position is permitted for the purpose of performing g
the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensionnd.
i I'
l
'i TABLE 4.3.4-1 w
CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS w
N Q
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TR1P FUNCTION AND INSTRUMENT NUMBER CH2CK TEST CALIBRATION SURVEILLANCE REQUIRED 1.
APRM (C51-APRh-CH.A,B C,D,E,F) 3 S/U((c)
R(b)(a) g a.
Upscale (Flow Biased)
NA.
l.,
S/U c)(E
,q(f)
NA 1,2,5 b.
Inoperative NA S/U((c)S/U c M
,q(d)(f) y g
c.
Downscale NA
)
R 2, 5 l
d.
Upscale (Fixed)
NA 2.
ROD' BLOCK MONITOR (C51-R8W-CH.A,B)
S/U(c)
R(a) g, S/U(c),M w
a.
Upscale NA y
3,
'S/U(c),q R a) 3, 3
b.
Inoperstive NA
,M w
c.
Downscale NA S.
l 3.
SOURCE RANCE MONITORS (C51-SRM-K600A,B,C,D)
(d)
S/U((c)S/U(c),g(d)
NA 2, 5 a.
Detector not full in HA i
g NA 2, 5 b.
Upscale NA S/U(c),g((d)
NA 2, 5 c.
Inoperative NA S/U c),g d)
NA 2, 5 d.
Dcwnscale NA 1
4.
INTERMEDIATE RANCE MONITORS (C51-IRM-K601A,B,C,D,E,F,C,H) c)(e),y(d)
NA 2
I a.
Detector not full in NA S
NA W
NA 5
h
.l b.
Upscale NA S/U(c),g(d)
NA
,2 NA W
NA 5
s w$
l
?"
c.
Inoperative NA S/U(c),y(d)
NA 2
NA W
NA 5
i
.o 4
ru d.
Downscale NA S/U(c),y(d)
NA 2
NA W
NA 5
i TABLE 4.3.4-1 (Cont'd) m
- o h
CONTROL ROD WITHDRAWAL' BIDCK INS 11tUMENTATION SURVEILLANCE REQUIREMENTS 6
CHANNEL OPERATIONAL
'Q CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
]
TRIP FUNCTION AND INSTRUMENT NUMBER CHECK
_ TEST __
CALIBRATION (a)
SURVEILLANCE REQUIRED.
5.
SCRAM DISCHARCE VOLUME (C12-LSH-N013E) s.
Water Level - High NA Q
R 1, 2, 5**
When THERMAL POWER is greater than the preset power level of the RWM and RSCS.
With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9 10.2.
(a) CHANNEL CALIBP.ArIONS are electronic.
(b) This calibration shall consist of the adjustment of the APKH flow biased setpoint us 30 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 Mays.
un (d) When changing from OPERATIONAL CONDITION 1 to OPERATIONAL CONDITION 2, perform the i
b' 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 OPERATIONAL CONDITION 2.
(e) Placement of Reactor Mode Switch into Startup/ Hot Standby position is permitted for the purpose of performing i
the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
(f) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of performing the required surveillance provided all control rods are fully inserted and the vessel head bolts are tensioned.
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- - - -