ML20210T391
| ML20210T391 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/01/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20210T396 | List: |
| References | |
| DPR-62-A-129, DPR-71-A-100 NUDOCS 8610080488 | |
| Download: ML20210T391 (10) | |
Text
__
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
j WASHINGTON, D. C. 20555
%,.....f CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Lignt Company (the licensee) dated May 6, 1985, as supplemented February 19, 1986 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 Cnapter I; B.
The facility will operate in conformity witn the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be intraical 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 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
8610090488 861001 PDR ADOCK 05000324 p
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.100, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Ad Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Uate of Issuance: October 1, 1986 m
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ATTACHMENT 10 LICENSE AMENDMENT NO. 100 FACILITY OPERATING LICENSE N0. DPR-71 DOCKET 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 3-8 3/4 3-8a
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E TABLE 4.3.1-l' (Continued) j si 5
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS R
j i
CHANNEL OPERATIONAL c
FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH I
AND INSTRUMENT NtMBER CHECK TEST CALIBRATION ")
SURVEILLANCE REQUIRED
- 5. Main Steam Line Isolation Valve -
NA M
R(h) 1 l
Closure I
(B21-F022A,B,C,D and j
B21-F028A,B,C,D)
- 6. Main Steam Line Radiation - High S
MII)
R(5) 1, 2 I
(D12-RM-K603A,B,C,D) 3g
- 7. Drywell Pressure - High
)
)
e (C71-PT-N002A,B,C,D)
NA NA R
1, 2 j
y (C71-PTM-NOO2A-1,B-1,C-1,D-1)
D M
M 1, 2 OD i
- 8. Scram Discharge Volume Water Level - High NA Q
R 1, 2, 5 (C11-LSH-N013A,B,C,D)
I j
(C11-LSH-4516A,B,C,D) l
- 9. Turbine Stop Valve - Closure NA M
R(h) g(o)
(EHC-SVOS-lX,2X,3X,4X)
- 10. Turbine Control Valve Fast j
Closure, Control Oil Pressure -
IO)
Low NA M
R I
)
f (EHC-PSL-1756,1757,1758,1759) e I
(
- 11. Reactor Mode Switch in Shutdown MA R
NA 1,2,3,4,5 u
Position f
[
(C71A-SI)
- 12. Manual Scram NA Q
NA 1,2,3,4,5
?^
(C71A-S3A,B)
[
I o
O
(BSEP-1-49) to TABLE 4.3.1-1 (Continued)
- o h
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
5 Q
(a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
i (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 d
(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 /> 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 to 25% of RATED THERMAL POWER.
(f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a u
Y calibrated flow signal.
u h
(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) Calibration using a standard radiation source.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.
g (1) Transmitters are exempted from the monthly channel calibration.
h (m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose of g
performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
n E
(n) Placement of Reactor Mode Switch into the Shutdown or Refuel position is permitted for the purpose of g
performing the required surveillance provided all control rods are fully inserted and the vessel head o*
bolts are tensioned.
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j (o) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.
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UNITED 8TATES
,8 NUCLEAR RESULATORY COMMISSION o
t a
cAsMNGTON, D. C. 20655
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENI TU FACILITY OPERATING LICENSE Amendment No. 129 License No. OPR-62
~ 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated May 6, 1985, as supplemented February 19, 1986 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 tac 111ty will operate 1n conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the publir, and (ii) that sucn activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and satety of the public; and E.
The issuance of this amendment is in accordance witn 10 CFR Part 51 of the Comission'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 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.129, 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.
FOR THE NUCLEAR REGULATORY COMMISSION f
//
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 1, 1986
~
D
ATTACHMENT TO LICENSE AMENDMENT N0.129 FACILITY OPERATING LICENSE N0. DPR-62 DOCKET NO. 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 3-8 3/4 3-8a
--m S
e W
(BSEP-2-45) a, E
TABLE 4.3.1-l'(Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS A
e CHANNEL,
OPERATIONAL l
c FUNCTIONAL UNIT CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH I
AND INSTRUMENT NUMBER CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED e
Ih)
- 5. Main Steam Line Isolation Valve -
NA M
R 1
Closure (B21-F022A,B,C,D and l
B21-F028A,B,C,D)
)
- 6. Main Steam Line Radiation - High S
M(I)
R(5) 1, 2 (D12-RM-K603A,B,C,D)
- 7. Dryvell Pressure - High ig (C72-PT-N002A,B,C,D)
NA(k)
NA RII) 1, 2 (C72-PTM-NOO2A-1,B-1,C-1,D-1)
D M
M 1, 2 Y
- 8. Scram Discharge Volume Water 00 Level - High NA Q
R 1,2,5 (Cl2-LSH-N013A,B,C,D)
(C12-LSH-4516A,B,C,D) l
- 9. Turbine Stop Valve - Closure NA M
R(h) j(o) l (EHC-SVOS-IX,2X,3X,4X)
- 10. Turbine Control Valve Fast Closure, Control Oil Pressure -
Low NA N
R 1(0) g (EHC-PSL-1756,1757,1758,1759) 5 g-
- 11. Reactor Mode Switch in Shutdown NA R
NA 1,2,3,4,5 Position g
(C72A-SI) g:
i
- 12. Manual Scram NA Q
NA 1,2,3,4,5 (C72A-S3A,B) 2
/
e.
.m i
1 (BSEP-2-45) i l
w TABLE 4.3.1-1 (Continued) wc:
M REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
Q (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.
l 8
(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.
i c:
l 5
H j
(c) The IRM channels shall be compared to the APRM channels and the SRM instruments for overlap during each j
startup, if not performed within the previous 7 days.
i (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.
1 (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 greater than or equal to 25% of RATED THERMAL POWER.
3d (f) This calibration shall consist of the adjustment of the APRM flow-biased setpoint to conform to a calibrated flow signal.
Y EP (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 (i) Instrument alignment using a standard current source.
t (j) Calibration using a standard radiation source.
(k) The transmitter channel check is satisfied by the trip unit channel check. A separate transmitter check is not required.
(1) Transmitters are exempted from the monthly channel calibration.
h (m) Placement of Reactor Mode Switch into the Startup/ Hot Standby position is permitted for the purpose cf g
performing the required surveillance prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.
a U
(n) 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.
U (o) Surveillance is not required when THERMAL POWER is less than 30% of RATED THERMAL POWER.
C e
I -
.